Basic requirements of nuclear medicine services

Energy Technology Data Exchange (ETDEWEB)

Belcher, E H

1993-12-31

Technological progress in nuclear medicine continues, not always to the immediate advantage of the developing world. The capital expense, operational demands and maintenance requirements of ever more complex equipment, the consequent need for highly trained staff, the necessity to assure regular supplies of costly radioactive materials, all present problems to which compromise or alternative solutions must often be sought. This chapter constitutes an attempt to define the basic requirements for thr practice of nuclear medicine with respect to staff, equipment, accommodation, supplies and supporting services with particular reference to the needs of institutions in developing countries

Basic requirements of nuclear medicine services

International Nuclear Information System (INIS)

Belcher, E.H.

1992-01-01

Technological progress in nuclear medicine continues, not always to the immediate advantage of the developing world. The capital expense, operational demands and maintenance requirements of ever more complex equipment, the consequent need for highly trained staff, the necessity to assure regular supplies of costly radioactive materials, all present problems to which compromise or alternative solutions must often be sought. This chapter constitutes an attempt to define the basic requirements for thr practice of nuclear medicine with respect to staff, equipment, accommodation, supplies and supporting services with particular reference to the needs of institutions in developing countries

Peculiarities of radionuclide contamination of different Semipalatinsk nuclear test site (SNTS) zones

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Khazhekber, S.; Lukashenko, S.N.; Solodukhin, V.P.; Kazachevskij, I.V.; Poznyak, V.L.; Knyazev, B.B.; Rofer, Ch.

2002-01-01

The Semipalatinsk Nuclear Test Site occupies about 18500 km 2 . There are 3 basic test zones in this territory including various test platforms where different character nuclear explosions were carried out. On the test platforms of the 'Opytnoe Pole' zone air and ground tests were performed, including nuclear and hydronuclear (without nuclear reaction) explosions. On the other zones (the Degelen mountains and Balapan valley) the underground tests including camouflaged and excavation nuclear explosions were carried out. Each kind of these tests can be characterised by the quantity and composition of radionuclides which were formed during the nuclear explosion, by the area of their distribution, localisation of the radionuclides at various sites, radionuclide species in soil. Transfer of the products of the air and the ground nuclear explosions by air flows and their sedimentation on the ground surfaces have caused broadband radioactive plumes extending over hundreds of kilometres. As a result of hydronuclear experiments, plenty of alpha-active radionuclides, consisting of a nuclear device is thrown locally out. Besides the ground and the air explosions, radiation conditions of the territory of the SNTS were influenced by excavation explosions with ground throwing out. Such tests resulted in an intensive local pollution. Other zone of an original pollution is the Degelen mountains. Although an basic mass of the nuclear explosion products is obviously concentrated in basin cavities of the tunnels, the radionuclides are taken out on a day time surface together with waters acting in the basin cavity of the tunnels. The results of investigation of radionuclide pollution on the various platforms of the SNTS territory are presented. The results characterise the radionuclide pollution by specificity of spent tests

Basic science of nuclear medicine

International Nuclear Information System (INIS)

Parker, R.P.; Taylor, D.M.; Smith, P.H.S.

1978-01-01

A book has been written presenting those aspects of physics, chemistry and related sciences which are essential to a clear understanding of the scientific basis of nuclear medicine. Part I covers the basic physics of radiation and radioactivity. Part II deals with radiation dosimetry, the biological effects of radiation and the principles of tracer techniques. The measurement of radioactivity and the principal aspects of modern instrumentation are presented in Part III. Those aspects of chemistry relevant to the preparation and use of radiopharmaceuticals are discussed in Part IV. The final section is concerned with the production of radionuclides and radiopharmaceuticals and with the practical aspects of laboratory practice, facilities and safety. The book serves as a general introductory text for physicians, scientists, radiographers and technicians who are entering nuclear medicine. (U.K.)

White Paper on Nuclear Data Needs and Capabilities for Basic Science

Energy Technology Data Exchange (ETDEWEB)

Batchelder, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kawano, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kelley, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kondev, F. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCutchan, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sonzogni, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thoennessen, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-05-14

Reliable nuclear structure and reaction data represent the fundamental building blocks of nuclear physics and astrophysics research, and are also of importance in many applications. There is a continuous demand for high-quality updates of the main nuclear physics databases via the prompt compilation and evaluation of the latest experimental and theoretical results. The nuclear physics research community benefits greatly from comprehensive, systematic and up-to-date reviews of the experimentally determined nuclear properties and observables, as well as from the ability to rapidly access these data in user-friendly forms. Such credible databases also act as a bridge between science, technology, and society by making the results of basic nuclear physics research available to a broad audience of users, and hence expand the societal utilization of nuclear science. Compilation and evaluation of nuclear data has deep roots in the history of nuclear science research, as outlined in Appendix 1. They have an enormous impact on many areas of science and applications, as illustrated in Figure 2 for the Evaluated Nuclear Structure Data File (ENSDF) database. The present workshop concentrated on the needs of the basic nuclear science community for data and capabilities. The main role of this community is to generate and use data in order to understand the basic nuclear forces and interactions that are responsible for the existence and the properties of all nuclides and, as a consequence, to gain knowledge about the origins, evolution and structure of the universe. Thus, the experiments designed to measure a wealth of nuclear properties towards these fundamental scientific goals are typically performed from within this community.

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

International Nuclear Information System (INIS)

Glasstone, S.; Sesonske, A.

1994-01-01

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

Basic Physics for Nuclear Medicine. Chapter 1

Energy Technology Data Exchange (ETDEWEB)

Podgorsak, E. B. [Department of Medical Physics, McGill University, Montreal (Canada); Kesner, A. L. [Division of Human Health, International Atomic Energy Agency, Vienna (Austria); Soni, P. S. [Medical Cyclotron Facility, Board of Radiation and Isotope Technology, Bhabha Atomic Research Centre, Mumbai (India)

2014-12-15

The technologies used in nuclear medicine for diagnostic imaging have evolved over the last century, starting with Röntgen’s discovery of X rays and Becquerel’s discovery of natural radioactivity. Each decade has brought innovation in the form of new equipment, techniques, radiopharmaceuticals, advances in radionuclide production and, ultimately, better patient care. All such technologies have been developed and can only be practised safely with a clear understanding of the behaviour and principles of radiation sources and radiation detection. These central concepts of basic radiation physics and nuclear physics are described in this chapter and should provide the requisite knowledge for a more in depth understanding of the modern nuclear medicine technology discussed in subsequent chapters.

Nuclear stress test

Science.gov (United States)

... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

Basic research on human reliability in nuclear power plants

International Nuclear Information System (INIS)

Zhang Li; Deng Zhiliang

1996-10-01

Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and ergonomic and on the bases of human cognitive behaviour characteristics, performance shaping factors, human error mechanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested feasible approaches and countermeasures for precaution against human factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design, operation and management in nuclear power plants. (11 refs.)

Underground Nuclear Testing Program, Nevada Test Site

International Nuclear Information System (INIS)

1975-09-01

The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport

International Nuclear Information System (INIS)

2007-11-01

This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

Basic research for nuclear energy. y Study on the nuclear materials technology

Energy Technology Data Exchange (ETDEWEB)

Kuk, I H; Lee, H S; Jeong, Y H; Sung, K W; Han, J H; Lee, J T; Lee, H K; Kim, S J; Kang, H S; An, D H; Kim, K R; Park, S D; Han, C H; Jung, M K; Oh, Y J; Kim, K H; Kim, S H; Back, J H; Kim, C H; Lim, K S; Kim, Y Y; Na, J W; Ku, J H; Lee, D H

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs.

Basic research for nuclear energy. y Study on the nuclear materials technology

International Nuclear Information System (INIS)

Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs

Basic study for development of nuclear heat application systems

Energy Technology Data Exchange (ETDEWEB)

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

1996-05-01

We need to intensely investigate real possibilities of nuclear heat application systems which exploit high potential of nuclear energy as a promising candidate of the future energy resource in the world. In this report, special interest was placed on coal reforming systems because we thought a compact heat source of nuclear power with a very high energy density might compensate the environmental problem caused by burning a great amount of coal. First, we reviewed state-of-the-art technologies for coal reforming technology with a special attention on coal gasification technologies. Based on these basic data, we proposed several nuclear coal reforming systems and discussed advantages and disadvantages of the systems. We also explored a model with which we could analyze nuclear heat application systems all together. In addition, we investigated possibility and effects of nuclear heat utilization systems producing chemical materials from carbon dioxide in flue gas of fossil fuel power plant. As a result, we showed nuclear heat application systems were useful. (author).

Basic metallurgy for nondestructive testing

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

For this chapter, reader will be served with the basic knowledge on metallurgy for nondestructive testing. One the main application of nondestructive testing is to detect discontinuity of mass defect in metal. As we already know, metal are widely used in many application such as in building as a system, component and engineering product. Steel and iron are metal that usually used in industry, especially heavy industry such as gas and petroleum industry, chemistry, electric generation, automobile, and military device. Based on this, basic knowledge on metallurgy must need by NDT practitioner. The combination between metallurgy and datas from radiography testing can make radiographer good interpretation on quality of the metal inspected and can used to make a good decision either to accept or not certain product, system or components.

US nuclear reaction data program in support of basic research

International Nuclear Information System (INIS)

Bhat, M.R.; Chadwick, M.B.; Smith, M.S.

1997-01-01

Information about the US Nuclear Reaction Data Network (USNRDN) such as its members, work in progress, summaries of meetings, and organizational details may be found in its WWW Homepage. This paper is an overview of the data support provided by the network for basic research in nuclear astrophysics, radioactive ion beams, high energy heavy-ion and electron interactions and related activities involving all aspects of data stewardship

Basic radiation knowledge for school education course. Nuclear technology seminar 2014 (Contract program)

International Nuclear Information System (INIS)

Watanabe, Yoko; Arai, Nobuyoshi; Sawada, Makoto; Kanaizuka, Seiichi; Shimada, Mayuka; Ishikawa, Tomomi; Nakamura, Kazuyuki

2015-11-01

Japan Atomic Energy Agency has conducted Nuclear Technology Seminar for Asian countries which plan to introduce nuclear power plant in future, in order to increase the number of engineers and specialists in nuclear related field. The Nuclear Technology Seminar on the Basic Radiation Knowledge for School Education Course was launched in 2012 due to increased recognition of the dissemination of the basic knowledge of radiation in public and education sectors as an important issue in the aftermath of the Fukushima Daiichi Nuclear Power Station Accident in 2011. It was the third time to conduct this course and fifteen trainees from eight Asian countries participated in 2014. In response to the requests of past participants, a new exercise 'Joint experiment with high school students' was introduced from 2014 to provide an international learning experience for the course participants and the local Japanese students by jointly conducting radiation related exercises. A new learning material was also developed in 2014 to help participants to study the basics of radiation in English. All the course activities including the details of preparatory process and course evaluation were described in this report. (author)

The development of basic glass formulations for solidifying HLW from nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Jiang Yaozhong; Tang Baolong; Zhang Baoshan; Zhou Hui

1995-01-01

Basic glass formulations 90U/19, 90U/20, 90Nd/7 and 90Nd/10 applied in electric melting process are developed by using the mathematical model of the viscosity and electric resistance of waste glass. The yellow phase does not occur for basic glass formulations 90U/19 and 90U/20 solidifying HLW from nuclear fuel reprocessing plant when the waste loading is 20%. Under the waste loading is 16%, the process and product properties of glass 90U/19 and 90U/20 come up to or surpass the properties of the same kind of foreign waste glasses, and other properties are about the same to them of foreign waste glasses. The process and product properties of basic glass formulations 90Nd/7 and 90Nd/10 used for the solidification of 'U replaced by Nd' liquid waste are almost similar to them of 90U/19 and 90U/20. These properties fairly meet the requirements of 'joint test' (performed at KfK-INE, Germany). Among these formulations, 90Nd/7 is applied in cold engineering scale electric melting test performed at KfK-INE in Germany. The main process properties of cold test is similar to laboratory results

An Embalse nuclear power plant basic principles simulator

International Nuclear Information System (INIS)

Fernandez, Oscar; Galdoz, Erwin; Flury, Celso; Fontanini, Horacio

1989-01-01

A nuclear power plant basic principles simulator is a package of programs that numerically solve the dynamic equations of the simulated plant. This kind of tools is mainly used in the first step of training of operational personnel, to allow mental representation of physical phenomena governing the plant. They are also used for students or professional training, and experienced operators can also improve there performance under abnormal operation situations using the simulator. For the Embalse nuclear power plant, mainly the thermohydraulic behaviour, is simulated. The mathematical model was adapted from MANUVR, a code developed at the Electric Systems and Control Department of the National Atomic Energy Commission (CNEA). (Author) [es

Validity of the ISUOG basic training test

DEFF Research Database (Denmark)

Hillerup, Niels Emil; Tabor, Ann; Konge, Lars

2018-01-01

A certain level of theoretical knowledge is required when performing basic obstetrical and gynecological ultrasound. To assess the adequacy of trainees' basic theoretical knowledge, the International Society of Ultrasound in Obstetrics and Gynecology (ISUOG) has developed a theoretical test of 49...... Multiple Choice Questionnaire (MCQ) items for their basic training courses....

Pump testing in the nuclear industry: The comprehensive test and other considerations

International Nuclear Information System (INIS)

Hoyle, T.F.

1992-01-01

The American Society of Mechanical Engineers Operations and Maintenance Working Group on Pumps and Valves is working on a revision to their pump testing Code, ISTB-1990. This revision will change the basic philosophy of pump testing in the nuclear industry. Currently, all pumps are required to be tested quarterly, except those installed in dry sumps. In the future standby pumps will receive only a start test quarterly to ensure the pump comes up to speed and pressure or flow. Then, on a biennial basis all pumps would receive a more extensive test. This comprehensive test would require high accuracy test gauges to be used, and the pumps would be required to be tested near pump design flow. Testing on minimum flow loops would not be permitted except in rare cases. Additionally. during the comprehensive test, measurements of vibration, flow, and pressure would all be taken. The OM-6 standard (ISTB Code) will also require that reference values of flow rate and differential pressure be taken at several points instead of just one point, which is current practice. The comprehensive test is just one step in ensuring the adequacy of pump testing in the nuclear industry. This paper also addresses other concerns and makes recommendations for increased quality of testing of certain critical pumps and recommendations for less stringent or no tests on less critical pumps

Revision of the basic plans of the first nuclear-powered ship development

International Nuclear Information System (INIS)

1978-01-01

Along with the law for Japan Nuclear Ship Development Agency, the basic plans of development of the first nuclear-powered ship have been revised. After explaining the basic policy concerning the matter, the development program is described as follows: ship type/kind, nuclear power plant, construction, training of ship crew, experimental voyage, compilation of the development results, and works after the experimental voyage. The first nuclear-powered ship of about 8,000 tons gross tonnage, 10,000 horsepower main engine output, and about 16 knots, sea speed will be the ship for special cargo transport and crew training. A pressurized water reactor is used for the power plant. Following the repair of shielding and the overall inspection of safety, the ship is to be completed as early as possible. After completion of the ship, its experimental voyage will be carried out, aiming at the aspects of operational familiarization, ship performance, reliability, port call experience, etc. (Mori, K

Basic concepts about application of dual vibration absorbers to seismic design of nuclear piping systems

International Nuclear Information System (INIS)

Hara, F.; Seto, K.

1987-01-01

The design value of damping for nuclear piping systems is a vital parameter in ensuring safety in nuclear plants during large earthquakes. Many experiments and on-site tests have been undertaken in nuclear-industry developed countries to determine rational design values. However damping value in nuclear piping systems is so strongly influenced by many piping parameters that it shows a tremendous dispersion in its experimental values. A new trend has recently appeared in designing nuclear pipings, where they attempt to use a device to absorb vibration energy induced by seismic excitation. A typical device is an energy absorbing device, made of a special material having a high capacity of plasticity, which is installed between the piping and the support. This paper deals with the basic study of application of dual vibration absorbers to nuclear piping systems to accomplish high damping value and reduce consequently seismic response at resonance frequencies of a piping system, showing their effectiveness from not only numerical calculation but also experimental evaluation of the vibration responses in a 3D model piping system equipped with dual two vibration absorbers

Some basic criteria for using of accountancy common system and nuclear material control

International Nuclear Information System (INIS)

Marzo, M.A.; Biaggio, A.L.

1994-01-01

Some basic criteria used by the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, using in the Accountancy and Control Common System of Nuclear Materials (SCCC) are presented and the control elements are described. The SCCC is a safeguard system used for all nuclear materials present in all nuclear activities executed by Brazil and Argentina. (C.G.C.). 4 refs, 1 tab

Proceedings of the meeting and scientific presentations on basic science research and nuclear technology

International Nuclear Information System (INIS)

Prayitno; Slamet Santosa; Darsono; Syarip; Agus Taftazani; Samin; Tri Mardji Atmono; Dwi Biyantoro; Herry Poernomo; Prajitno; Tjipto Sujitno; Gede Sutresna W; Djoko Slamet Pujorahardjo; Budi Setiawan; Bambang Siswanto; Endro Kismolo; Jumari

2016-08-01

The Proceedings of the Meeting and Scientific Presentations on Basic Science Research and Nuclear Technology by Center for Accelerator Science and Technology in Yogyakarta with the theme of Universities and research and development institutions synergy in the development of basic science and nuclear technology held on Surakarta 9 August 2016. This seminar is an annual routine activities of Center for Accelerator Science and Technology for exchange research result among University and BATAN researcher for using nuclear technology. The proceeding consist of 3 article from keynotes’ speaker and 37 articles from BATAN participant as well as outside which have been indexed separately. (MPN)

U.S. nuclear reaction data program in support of basic research

International Nuclear Information System (INIS)

Bhat, M.R.; Chadwick, M.B.; Smith, M.S.

1998-03-01

Information about the US Nuclear Reaction Data Network (USNRDN) such as its members, work in progress, summaries of meetings, and organizational details may be found in its WWW Homepage. This paper is an overview of the data support provided by the network for basic research in nuclear astrophysics, radioactive ion beams, high energy heavy ion and electron interactions and related activities involving all aspects of data stewardship

Nuclear Test Personnel Review

Science.gov (United States)

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

The first international training course on basic nuclear forensic methodologies for practitioners

International Nuclear Information System (INIS)

Schwantes, Jon M.; Smith, David K.

2013-01-01

The IAEA, in cooperation with the United States National Nuclear Security Administration, developed and conducted the first international training course on basic nuclear forensic methodologies for practitioners in 2012. An overview of the major elements of this landmark workshop as well as successes and recommendations for future improvement are presented here. (author)

The basic discussion on nuclear power safety improvement based on nuclear equipment design

International Nuclear Information System (INIS)

Zhao Feiyun; Yao Yangui; Yu Hao; He Yinbiao; Gao Lei; Yao Weida

2013-01-01

The safety of strengthening nuclear power design was described based on nuclear equipment design after Fukushima nuclear accident. From these aspects, such as advanced standard system, advanced design method, suitable test means, consideration of beyond design basis event, and nuclear safety culture construction, the importance of nuclear safety improvement was emphatically presented. The enlightenment was given to nuclear power designer. (authors)

Political aspects of nuclear test effects at Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Sydykov, E.B.; Panin, M.S.

2003-01-01

The paper describes tense struggle of Kazakhstan people for closure of the Semipalatinsk Nuclear Test Site. It reveals major foreign policy aspects and nuclear test effects for both Kazakhstan and the world community. (author)

The nuclear envelope from basic biology to therapy.

Science.gov (United States)

Worman, Howard J; Foisner, Roland

2010-02-01

The nuclear envelope has long been a focus of basic research for a highly specialized group of cell biologists. More recently, an expanding group of scientists and physicians have developed a keen interest in the nuclear envelope since mutations in the genes encoding lamins and associated proteins have been shown to cause a diverse range of human diseases often called laminopathies or nuclear envelopathies. Most of these diseases have tissue-selective phenotypes, suggesting that the nuclear envelope must function in cell-type- and developmental-stage-specific processes such as chromatin organization, regulation of gene expression, controlled nucleocytoplasmic transport and response to stress in metazoans. On 22-23 April 2009, Professor Christopher Hutchison organized the 4th British Nuclear Envelope Disease and Chromatin Organization meeting at the College of St Hild and St Bede at Durham University, sponsored by the Biochemical Society. In attendance were investigators with one common interest, the nuclear envelope, but with diverse expertise and training in animal and plant cell biology, genetics, developmental biology and medicine. We were each honoured to be keynote speakers. This issue of Biochemical Society Transactions contains papers written by some of the presenters at this scientifically exciting meeting, held in a bucolic setting where the food was tasty and the wine flowed freely. Perhaps at the end of this excellent meeting more questions were raised than answered, which will stimulate future research. However, what became clear is that the nuclear envelope is a cellular structure with critical functions in addition to its traditional role as a barrier separating the nuclear and cytoplasmic compartments in interphase eukaryotic cells.

Basic plans of nuclear energy development and utilization for fiscal 1982 (report)

International Nuclear Information System (INIS)

1982-01-01

A report by the Nuclear Safety Commission to the Prime Minister, concerning the basic plans of nuclear energy development and utilization for fiscal 1982, was presented; the NSC has decided on the plans drawn up by the Prime Minister. Nuclear power generation as the nucleus of petroleum substitutes must be developed steadily. For the purpose, nuclear fuel cycle should be established, including the securing of uranium resources, uranium enrichment, fuel reprocessing, and waste management. The contents are as follows: the strengthening of nuclear safety measures, the promotion of nuclear power generation, the establishment of nuclear fuel cycle, the development of advanced types of reactors, the research on nuclear fusion, the research and development of nuclear powered ships, the promotion of radiation utilization, the strengthening of basis for nuclear energy development and utilization, the promotion of international cooperation, the strengthening of safeguard and nuclear material protection measures, fiscal 1982 budgets related to nuclear energy. (Mori, K.)

Propagation of uncertainties from basic data to key parameters of nuclear reactors

International Nuclear Information System (INIS)

Kodeli, I.

2010-01-01

The author reports the development of a set of computing software (SUSD3D) and of libraries of nuclear data covariance matrices to assess sensitivities of parameters with respect to basic nuclear data, and the corresponding uncertainties, notably for radiation transport for which uncertainty has various origins: reactivity coefficients or neutron and gamma ray flows. He reports the application to fusion and fission reactors

Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology. Part I : Physics, Reactor Physics and Nuclear Instrumentation

International Nuclear Information System (INIS)

Sudjatmoko; Karmanto, Eko Edy; Supartini, Endang

1996-04-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity was held by PPNY BATAN for monitoring the research Activity which achieved in BATAN. The Proceeding contains a proposal about basic which has physics; reactor physics and nuclear instrumentation. This proceedings is the first part from two part which published in series. There are 33 articles which have separated index

Preparation of nuclear grade strongly basic anion exchange resin in hydroxide from

International Nuclear Information System (INIS)

Ke Weiqing

1989-01-01

The two-step transformation method was used to prepare 90 kg nuclear grade strongly basic anion exchange resins by using the industrial grade baking soda and caustic soda manufacutred by mercury-cathode electrolysis. The chloride and biscarbonate fraction on resin is 0.8% and 1.25% respectively, when the baking soda and caustic soda consumption is 8.6 and 13.7 times the total exchange capacity of the strongly basic resin

Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology part II : Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

International Nuclear Information System (INIS)

Sukarsono, R.; Ganang Suradjijo

2002-01-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. This proceedings contains a proposal about basic research in nuclear technology which has environment. This proceedings is the second part of the two parts which published in series. There are 57 articles which have separated index. (PPIN)

Asia nuclear-test-ban network for nuclear non-proliferation

International Nuclear Information System (INIS)

Shinohara, Nobuo; Kokaji, Lisa; Ichimasa, Sukeyuki

2010-01-01

In Global Center of Excellence Program of The University of Tokyo, Non- Proliferation Study Committee by the members of nuclear industries, electricity utilities, nuclear energy institutes and universities has initiated on October 2008 from the viewpoints of investigating a package of measures for nuclear non-proliferation and bringing up young people who will support the near-future nuclear energy system. One of the non-proliferation issues in the Committee is the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Objective of this treaty is to cease all nuclear weapon test explosions and all other nuclear explosion. This purpose should be contributed effectively to the political stability of the Asian region by continuous efforts to eliminate the nuclear weapons. In the Committee, by extracting several issues related to the CTBT, conception of 'Asia nuclear-test-ban network for nuclear non-proliferation' has been discussed with the aim of the nuclear-weapon security in Asian region, where environmental nuclear-test monitoring data is mainly treated and utilized. In this paper, the conception of the 'network' is presented in detail. (author)

Development of nuclear counting system for plateau high voltage scintillation detector test facilities

International Nuclear Information System (INIS)

Sarizah Mohamed Nor; Siti Hawa Md Zain; Muhd Izham Ahmad; Izuhan Ismail

2010-01-01

Nuclear counter system is a system monitoring and analysis of radioactivity used in scientific and technical research and development in the Malaysian Nuclear Agency. It consists of three basic parts, namely sensors, signal conditioning and monitoring. Nuclear counter system set up for use in the testing of nuclear detectors using radioactive sources such as 60 Co and 137 Cs and other radioactive sources. It can determine the types of scintillation detectors and the equivalent function properly, always operate in the range plateau high voltage and meet the specifications. Hence, it should be implemented on all systems in the Nuclear Nuclear counter Malaysia and documented as Standard Working Procedure (SWP) is a reference to the technicians, trainees IPTA / IPTS and related workers. (author)

Monitored course at distance Nuclear Medicine: Introduction of Basic Physics Aspects. Preliminary results

International Nuclear Information System (INIS)

Lopez Diaz, A.; San Pedro, A.P.; Petrirena, G.

2007-01-01

Full text: This project try to evaluated the use of specialized multimedia product for a monitored education at distance of personnel who start to be close related with Nuclear Medicine Techniques like nurse, surgeons, specialized physician, oncologist, etc. The multimedia product included two items: Introduction to Nuclear Medicine Techniques and Basic aspects of radiation physics. Each item contents an audio visual conference (Power Point) and a charter (PDF): with theoretic aspects, understand verification questions and self-evaluation activities. The product need only a PC compatible with window 98 (or more advanced version), and 130MBy of memory spaced for archive. In order to verify the effectiveness of the distance course, we tested its results in 4 specialists: 1 nurse, 1 radio-pharmacist, 1 cardiologist and 1 neurologist. After consult and clarify their doubts, a final test was applied in order to check the knowledge acquired. With 100 point of maximum score and 60-point minimum to pass, the test contented 2 types of questions: true or false choice (with 50 aspects to verify, 1.5 point/ correct answer) and many correct choices (5 questions, 5 point/correct answer). The average result was 91.5 points/ students (89.5- 94 points); the four students pass the test with very good degree of comprehension (1 very good and 3 excellent). The course was polled about the quality of the material and their comprehension degree, asking the student to make suggestions if were needed. The average evaluation was 94 points (91-95 points). The suggestions made were: increase the number of examples and practical sequences, the understand verification questions and include monitored practical exercise. Conclusion: the product can be useful for a monitored education at distance of personnel who start to be related with Nuclear Medicine Techniques. Recommendation: The program should be enrich with the suggested things and extend to other important items like: radiation protection

The new technologies and infrastructure conversion of nuclear testing in Kazakhstan

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.

1999-01-01

use former nuclear test site as world test site in view of International cooperation in development of effective techniques of control for nuclear test over the world. In the paper is emphasized, that in Kazakhstan nuclear-physics studies in the main are carrying out in Inst. of Nuclear Physics. The Inst. was found in 1957. At present it incorporates 16 scientific laboratories and has its branch in Western Kazakhstan. The basic experimental facilities used for studies are the isochronous cyclotron U-150, the heavy ion accelerator UKR-2-1 and research nuclear reactor WWR-K. The main areas of studies: fundamental nuclear physics; applied nuclear physics in the fields of radiation materials science and radiology

Basic safety principles for nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

Nuclear power plant safety requires a continuing quest for excellence. All individuals concerned should constantly be alert to opportunities to reduce risks to the lowest practicable level. The quest, however, is most likely to be fruitful if it is based on an understanding of the underlying objectives and principles of nuclear safety, and the way in which its aspects are interrelated. This report is an attempt to provide a logical framework for such an understanding. The proposed objectives and principles of nuclear safety are interconnected and must be taken as a whole; they do not constitute a menu from which selection can be made. The report takes account of current issues and developments. It includes the concept of safety objectives and the use of probabilistic safety assessment. Reliability targets for safety systems are discussed. The concept of a 'safety culture' is crucial. Attention has been paid to the need for planning for accident management. The report contains objectives and principles. The objectives state what is to be achieved; the principles state how to achieve it. In each case, the basic principle is stated as briefly as possible. The accompanying discussion comments on the reasons for the principle and its importance, as well as exceptions, the extent of coverage and any necessary clarification. The discussion is as important as the principle it augments. 4 figs

Basics of radiobiology and nuclear medicine

International Nuclear Information System (INIS)

Kostadinova, I.; Hadjidekova, V.; Georgieva, R.

2002-01-01

The authors successively reveal the topics of the biological impact of radiation (radiobiology) and the diagnostic and the therapeutic application of radiopharmaceuticals (nuclear medicine). Data on the influence of radiation on subcellular, cellular, tissue and organ level are given, on early and late radiation changes, as well. Indication for the application of the different radionuclide methods in the diagnosis of the diseases in the endocrinology, nephrology, cardiology, gastroenterology, haematology of lungs, bones, tumors are pointed out and the main trends of the growing therapeutical use of nuclear medicine are presented. The aim is to teach students the nuclear medicine methods in the complex investigation of the patients, his preliminary preparation and the biological impact of radiation and its risk. Self assessment test for students are proposed and a literature for further reading

Manual on nuclear gauges. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1992-01-01

In addition to a basic guide to the principles of production of ionizing radiation and to the methods of radiation protection and dosimetry, this booklet considers the procedures that should be employed when using nuclear gauges. Applications for such gauges are described and radiation protection procedures discussed

Basic requirements of mechanical properties for nuclear pressure vessel materials in ASME-BPV code

International Nuclear Information System (INIS)

Ning Dong; Yao Weida

2011-01-01

The four basic aspects of strengths, ductility, toughness and fatigue strengths can be summarized for overall mechanical properties requirements of materials for nuclear pressure-retaining vessels in ASME-BPV code. These mechanical property indexes involve in the factors of melting, manufacture, delivery conditions, check or recheck for mechanical properties and chemical compositions, etc. and relate to degradation and damage accumulation during the use of materials. This paper specifically accounts for the basic requirements and theoretic basis of mechanical properties for nuclear pressure vessel materials in ASME-BPV code and states the internal mutual relationships among the four aspects of mechanical properties. This paper focuses on putting forward at several problems on mechanical properties of materials that shall be concerned about during design and manufacture for nuclear pressure vessels according to ASME-BPV code. (author)

Nuclear energy basic knowledge

International Nuclear Information System (INIS)

Volkmer, Martin

2013-11-01

The following topics are dealt with: Atoms, nuclear decays and radioactivity, energy, nuclear fission and the chain reaction, controlled nuclear fission, nuclear power plants, safety installations in nuclear power plants, fuel supply and disposal, radiation measurement and radiation exposition of man. (HSI)

The quantitative assessment of the role played by basic amino acid clusters in the nuclear uptake of human ribosomal protein L7

International Nuclear Information System (INIS)

Tai, Lin-Ru; Chou, Chang-Wei; Lee, I-Fang; Kirby, Ralph; Lin, Alan

2013-01-01

In this study, we used a multiple copy (EGFP) 3 reporter system to establish a numeric nuclear index system to assess the degree of nuclear import. The system was first validated by a FRAP assay, and then was applied to evaluate the essential and multifaceted nature of basic amino acid clusters during the nuclear import of ribosomal protein L7. The results indicate that the sequence context of the basic cluster determines the degree of nuclear import, and that the number of basic residues in the cluster is irrelevant; rather the position of the pertinent basic residues is crucial. Moreover, it also found that the type of carrier protein used by basic cluster has a great impact on the degree of nuclear import. In case of L7, importin β2 or importin β3 are preferentially used by clusters with a high import efficiency, notwithstanding that other importins are also used by clusters with a weaker level of nuclear import. Such a preferential usage of multiple basic clusters and importins to gain nuclear entry would seem to be a common practice among ribosomal proteins in order to ensure their full participation in high rate ribosome synthesis. - Highlights: ► We introduce a numeric index system that represents the degree of nuclear import. ► The rate of nuclear import is dictated by the sequence context of the basic cluster. ► Importin β2 and β3 were mainly responsible for the N4 mediated nuclear import

The quantitative assessment of the role played by basic amino acid clusters in the nuclear uptake of human ribosomal protein L7

Energy Technology Data Exchange (ETDEWEB)

Tai, Lin-Ru [Institute of Genome Sciences, National Yang-Ming University, Taipei, Taiwan, ROC (China); Chou, Chang-Wei [Institute of Clinical Dentistry Science, National Yang-Ming University, Taipei, Taiwan, ROC (China); Lee, I-Fang; Kirby, Ralph [Institute of Genome Sciences, National Yang-Ming University, Taipei, Taiwan, ROC (China); Lin, Alan, E-mail: alin@ym.edu.tw [Institute of Genome Sciences, National Yang-Ming University, Taipei, Taiwan, ROC (China); Institute of Clinical Dentistry Science, National Yang-Ming University, Taipei, Taiwan, ROC (China)

2013-02-15

In this study, we used a multiple copy (EGFP){sub 3} reporter system to establish a numeric nuclear index system to assess the degree of nuclear import. The system was first validated by a FRAP assay, and then was applied to evaluate the essential and multifaceted nature of basic amino acid clusters during the nuclear import of ribosomal protein L7. The results indicate that the sequence context of the basic cluster determines the degree of nuclear import, and that the number of basic residues in the cluster is irrelevant; rather the position of the pertinent basic residues is crucial. Moreover, it also found that the type of carrier protein used by basic cluster has a great impact on the degree of nuclear import. In case of L7, importin β2 or importin β3 are preferentially used by clusters with a high import efficiency, notwithstanding that other importins are also used by clusters with a weaker level of nuclear import. Such a preferential usage of multiple basic clusters and importins to gain nuclear entry would seem to be a common practice among ribosomal proteins in order to ensure their full participation in high rate ribosome synthesis. - Highlights: ► We introduce a numeric index system that represents the degree of nuclear import. ► The rate of nuclear import is dictated by the sequence context of the basic cluster. ► Importin β2 and β3 were mainly responsible for the N4 mediated nuclear import.

Finnish solution to increased basic professional training needs in nuclear safety

International Nuclear Information System (INIS)

Kyrki-Ramaeki, R.; Koskinen, K.

2008-01-01

The Finnish nuclear energy organizations have in cooperation arranged basic professional training courses on nuclear safety due to fast increased education needs. Especially the new nuclear power plant construction project turned the situation acute, but there was also a need to preserve the tacit knowledge of many nuclear experts retiring within the next ten years. From 2003, the YK courses have been arranged five times with altogether 270 participants. The need of this kind of complementary education is still seen high in Finland, and the YK6 course is to be arranged during the next winter. There has not been seen to be legal incompetence due to the likelihood of bias in the education even that the participating organizations have differing and/or opposing roles. It is seen that a real safety culture presumes that nuclear safety is a common goal, and even the competition for market shares is no obstacle for cooperation. (authors)

Basic tendencies of restructured UO2 nuclear fuels fabrication industry for water-moderated reactors

International Nuclear Information System (INIS)

Makhova, V.A.; Bokshitskij, V.I.; Blinova, I.V.

2002-01-01

Processes of reformation and consolidation of firms and frontier nuclear fuels fabrication industry associated with processes of globalization and deregulation of electric power market are analyzed. Current state of nuclear fuel market and basic factors influenced on the market are presented. The role of nuclear fuel in increasing competition of NPP and fundamental directions of innovation action on the creation of perspective kinds of fuel were considered [ru

Basic principles for intervention after a nuclear or radiological emergency

International Nuclear Information System (INIS)

Per Hedemann Jensen

1996-01-01

The current status of internationally agreed principles for intervention after a nuclear accident or radiological emergency and the international development of intervention guidance since the Chernobyl accident are reviewed. The experience gained after the Chernobyl accident indicates that the international advice on intervention existing at the time of the Chernobyl accident was not fully understood by decision makers neither in Western Europe nor in the former USSR and that the guidance failed to address adequately the difficult social problems which can arise after a serious nuclear accident. The radiation protection philosophy of today distinguishes between practices and interventions. The radiological protection system of intervention includes justification of the protective action and optimization of the level of protection achieved by that action. Dose limits do not apply in intervention situations. The inputs to justification and optimization studies include factors that are related to radiological protection, whereas the final decisions on introduction of countermeasures would also depend on other factors. The basic principles for intervention as recommended by international organisations are discussed in detail and the application of the principles on a generic basis is illustrated for long-term protective actions. The concepts of intervention level, operational intervention level and action level are presented and the relation between these quantities is illustrated. The numerical guidance on intervention in a nuclear accident or radiological emergency or a chronic exposure situation given by ICRP, IAEA and in the Basic Safety Standards is presented. (author)

Nuclear Fuel Test Rod Fabrication for Data Acquisition Test

International Nuclear Information System (INIS)

Joung, Chang-Young; Hong, Jin-Tae; Kim, Ka-Hye; Huh, Sung-Ho

2014-01-01

A nuclear fuel test rod must be fabricated with precise welding and assembly technologies, and confirmed for their soundness. Recently, we have developed various kinds of processing systems such as an orbital TIG welding system, a fiber laser welding system, an automated drilling system and a helium leak analyzer, which are able to fabricate the nuclear fuel test rods and rigs, and keep inspection systems to confirm the soundness of the nuclear fuel test rods and rids. The orbital TIG welding system can be used with two kinds of welding methods. One can perform the round welding for end-caps of a nuclear fuel test rod by an orbital head mounted in a low-pressure chamber. The other can do spot welding for a pin-hole of a nuclear fuel test rod in a high-pressure chamber to fill up helium gas of high pressure. The fiber laser welding system can weld cylindrical and 3 axis samples such as parts of a nuclear fuel test rod and instrumentation sensors which is moved by an index chuck and a 3 axis (X, Y, Z) servo stage controlled by the CNC program. To measure the real-time temperature change at the center of the nuclear fuel during the irradiation test, a thermocouple should be instrumented at that position. Therefore, a hole needs to be made at the center of fuel pellet to instrument the thermocouple. An automated drilling system can drill a fine hole into a fuel pellet without changing tools or breaking the work-piece. The helium leak analyzer (ASM-380 model of DEIXEN Co.) can check the leak of the nuclear fuel test rod filled with helium gas. This paper describes not only the assembly and fabrication methods used by the process systems, but also the results of the data acquisition test for the nuclear fuel test rod. A nuclear fuel test rod for the data acquisition test was fabricated using the welding and assembling echnologies acquired from previous tests

Nuclear Fuel Test Rod Fabrication for Data Acquisition Test

Energy Technology Data Exchange (ETDEWEB)

Joung, Chang-Young; Hong, Jin-Tae; Kim, Ka-Hye; Huh, Sung-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

A nuclear fuel test rod must be fabricated with precise welding and assembly technologies, and confirmed for their soundness. Recently, we have developed various kinds of processing systems such as an orbital TIG welding system, a fiber laser welding system, an automated drilling system and a helium leak analyzer, which are able to fabricate the nuclear fuel test rods and rigs, and keep inspection systems to confirm the soundness of the nuclear fuel test rods and rids. The orbital TIG welding system can be used with two kinds of welding methods. One can perform the round welding for end-caps of a nuclear fuel test rod by an orbital head mounted in a low-pressure chamber. The other can do spot welding for a pin-hole of a nuclear fuel test rod in a high-pressure chamber to fill up helium gas of high pressure. The fiber laser welding system can weld cylindrical and 3 axis samples such as parts of a nuclear fuel test rod and instrumentation sensors which is moved by an index chuck and a 3 axis (X, Y, Z) servo stage controlled by the CNC program. To measure the real-time temperature change at the center of the nuclear fuel during the irradiation test, a thermocouple should be instrumented at that position. Therefore, a hole needs to be made at the center of fuel pellet to instrument the thermocouple. An automated drilling system can drill a fine hole into a fuel pellet without changing tools or breaking the work-piece. The helium leak analyzer (ASM-380 model of DEIXEN Co.) can check the leak of the nuclear fuel test rod filled with helium gas. This paper describes not only the assembly and fabrication methods used by the process systems, but also the results of the data acquisition test for the nuclear fuel test rod. A nuclear fuel test rod for the data acquisition test was fabricated using the welding and assembling echnologies acquired from previous tests.

Basic data, computer codes and integral experiments: The tools for modelling in nuclear technology

International Nuclear Information System (INIS)

Sartori, E.

2001-01-01

When studying applications in nuclear technology we need to understand and be able to predict the behavior of systems manufactured by human enterprise. First, the underlying basic physical and chemical phenomena need to be understood. We have then to predict the results from the interplay of the large number of the different basic events: i.e. the macroscopic effects. In order to be able to build confidence in our modelling capability, we need then to compare these results against measurements carried out on such systems. The different levels of modelling require the solution of different types of equations using different type of parameters. The tools required for carrying out a complete validated analysis are: - The basic nuclear or chemical data; - The computer codes, and; - The integral experiments. This article describes the role each component plays in a computational scheme designed for modelling purposes. It describes also which tools have been developed and are internationally available. The role of the OECD/NEA Data Bank, the Radiation Shielding Information Computational Center (RSICC), and the IAEA Nuclear Data Section are playing in making these elements available to the community of scientists and engineers is described. (author)

Basic Characteristics of Human Erroneous Actions during Test and Maintenance Activities Leading to Unplanned Reactor Trips

International Nuclear Information System (INIS)

Kim, Jae Whan; Park, Jin Kyun

2010-01-01

Test and maintenance (T and M) activities of nuclear power plants are essential for sustaining the safety of a power plant and maintaining the reliability of plant systems and components. However, the potential of human errors during T and M activities has also the potential to induce unplanned reactor trips or power derate or making safety-related systems unavailable. According to the major incident/accident reports of nuclear power plants in Korea, contribution of human errors takes up about 20% of the total events. The previous study presents that most of human-related unplanned reactor trip events during normal power operation are associated with T and M activities (63%), which are comprised of plant maintenance activities such as a 'periodic preventive maintenance (PPM)', a 'planned maintenance (PM)' and a 'corrective maintenance (CM)'. This means that T and M activities should be a major subject for reducing the frequency of human-related unplanned reactor trips. This paper aims to introduce basic characteristics of human erroneous actions involved in the test and maintenance-induced unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants. The basic characteristics are described by dividing human erroneous actions into planning-based errors and execution-based errors. For the events associated with planning failures, they are, firstly, classified according to existence of the work procedure and then described for what aspects of the procedure or work plan have deficiency or problem. On the other hand, for the events associated with execution failures, they are described from the aspect of external error modes

The analysis on the basic technology and radiation induced voltaic mechanism for nuclear battery

Energy Technology Data Exchange (ETDEWEB)

Hwang, Woan; Lee, B. O.; Min, B. T.; Kang, H. Y.; Kim, B. H.; Park, J. H.; Seo, H. S

2000-12-01

Present study is for nuclear battery technology directly converting radiation energy to electricity among various nuclear energy, and it is anticipated that an interest in direct conversion of nuclear energy into electricity shall be increased as the conversion efficiency enhances. The battery should promise cheap, reliable power from a package small and light enough to be mobile, and with energy density great enough for use as a space based power supply. Various radiation-electricity conversion mechanism so far have been reported since G.J. Moseley reported the operation of a high-voltage nuclear battery using radium. The most important conversion mechanisms are RTG (Radioisotope Thermoelectric Generator) converting the heat produced from radioisotope to electricity using the temperature difference, and NRG (Nuclear Resonance Generator) using free electrons from the collision between {alpha}, {beta}rays and copper coil. It is well known that RTG and NRG mechanisms are most practical way because their efficiencies high. The basic technology on radiation-electricity conversion mechanism, interaction mechanism between {beta} ray and material, shielding for {beta} ray, and technical backgrounds and a state of the art for RTG and NRG technologies, are analyzed in this report. Basic data on the conceptual design for the prototype of nuclear battery are prepared.

The analysis on the basic technology and radiation induced voltaic mechanism for nuclear battery

International Nuclear Information System (INIS)

Hwang, Woan; Lee, B. O.; Min, B. T.; Kang, H. Y.; Kim, B. H.; Park, J. H.; Seo, H. S.

2000-12-01

Present study is for nuclear battery technology directly converting radiation energy to electricity among various nuclear energy, and it is anticipated that an interest in direct conversion of nuclear energy into electricity shall be increased as the conversion efficiency enhances. The battery should promise cheap, reliable power from a package small and light enough to be mobile, and with energy density great enough for use as a space based power supply. Various radiation-electricity conversion mechanism so far have been reported since G.J. Moseley reported the operation of a high-voltage nuclear battery using radium. The most important conversion mechanisms are RTG (Radioisotope Thermoelectric Generator) converting the heat produced from radioisotope to electricity using the temperature difference, and NRG (Nuclear Resonance Generator) using free electrons from the collision between α, βrays and copper coil. It is well known that RTG and NRG mechanisms are most practical way because their efficiencies high. The basic technology on radiation-electricity conversion mechanism, interaction mechanism between β ray and material, shielding for β ray, and technical backgrounds and a state of the art for RTG and NRG technologies, are analyzed in this report. Basic data on the conceptual design for the prototype of nuclear battery are prepared

Current developments in mechanized non-destructive testing in nuclear power plants

International Nuclear Information System (INIS)

Zeilinger, R.

2008-01-01

Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

Utilization of El Dabaa basic simulator for manpower development

International Nuclear Information System (INIS)

Wahab, W.A.; Abdel Hamid, S.B.

1998-01-01

Training with basic simulators is considered as an essential tool for training and retraining of the nuclear power plant staff. To achieve that objective; Nuclear Power Plants Authority (NPPA) has installed a basic training simulator for PWR and PHWR simulation at El Dabaa site. The basic simulator simulates a 3-loops PWR-900 MW(e) and 2-loops PHWR-600 MW(e). The simulator has passed in-plant acceptance tests in CEA/CENG, Grenoble, France and passed successfully on-site completion tests at El Dabaa site in November 1991. This paper presents the main features of the simulator; training capabilities, hardware configuration and software architectures. Also training methodology by NPPA and the training experience gained by using the simulator are presented. (author)

Decades of nuclear testing

International Nuclear Information System (INIS)

Miettinen, J.K.

1995-01-01

The United States carried out the world's first nuclear test in 1945. The test marked the beginning of an arms race between the great powers that lasted for decades. Innumerable nuclear test explosions were detonated to test and refine the weapons. The arms race picked up speed in the 1950s and culminated in 1958, when the United States detonated 77 and the Soviet Union 35 nuclear explosions. This was followed by the first pause in nuclear testing, brought about through the efforts of the Pugwash organisation consisting of the world's foremost scientists. Finland, too, received its share of the radioactive fallout coming from atmospheric nuclear explosions. Rain water samples have been studied for radioactivity in Finland since the mid-1950s. The first studies to determine the internal radiation doses caused by radioactive substances in man were conducted in the late 1950s by measuring cesium and strontium contents in grass and in milk. The efficiency of research and radiation monitoring improved in the 1960s, which was also a time when training in the sector developed rapidly. In consequence, when the accident in Chernobyl took place Finland had already gained valuable experience needed for rapid determination of unexpected fallout. (orig.) (3 figs.)

Relationship between basic nuclear data and LWR fuel cycle parameters

International Nuclear Information System (INIS)

Becker, M.; Harris, D.R.; Quan, B.; Ryskamp, J.M.

1979-01-01

An interactive system has been developed at RPI to analyze the sensitivity of water reactor fuel cycle parameters and costs to uncertainties in nuclear data. A sequence of batch depletion, core analysis, and fuel cost codes (referred to as Path B) determines the changes in fuel cycle parameters and costs for changes in few-group microscopic cross sections, in fission yields, and in decay data. For cases that are found to be significant from Part B analysis, the sensitivities of few-group data to basic nuclear data are determined by detailed calculations (referred to as Path A). Analyses of pressurized and boiling water reactors with recycle and throwaway options show substantial sensitivities of fuel cycle parameters and costs, particularly to thermal and resonance nuclear data for fissile nuclides. The results bring out the importance for power reactor sensitivity analysis of dealing with the full fuel cycle including depletion of initially-loaded fuel and the building-in of actinides and fission products

Taking into account chemical safety for French basic nuclear installations

International Nuclear Information System (INIS)

Tabard, Laurence; Conte, Dorothee

2013-01-01

Among nuclear installations, some fuel cycle facilities present a high level of chemical hazards. In France, the TSN law of the 13 June 2006 requires taking into account all the risks generated by a basic nuclear installation (BNI). But, as most of the implementing regulatory texts are under development at this time, part of the previous regulation settled down in the 1990's is still applying: the order of the 31 December 1999 concerning technical regulation in order to prevent and to limit hazards generated by nuclear facilities; the decree of the 4 May 1995 and the order of the 26 November 1999 that deal with BNI discharges. Moreover, some parts of BNI or of nuclear sites can be submitted to the general regulation concerning chemical hazards, which is part of the environment code. As a result, even if the TSN law and its implementing decree Nr 2007-1557 of the 2 November 2007 settle clearly that safety of BNI is not only radiological, but must take into account chemical hazards, the latter aspects are still under development. Moreover the application of the existing regulation, even if complex, has helped to assess chemical risks inside BNI and nuclear sites. (authors)

A comprehensive nuclear test ban

International Nuclear Information System (INIS)

1985-01-01

The conclusion of a comprehensive nuclear test ban is of critical importance for the future of arms limitation and disarmament. As the 1980 report of the Secretary-General concluded, a comprehensive nuclear test ban is regarded as the first and most urgent step towards the cessation of the nuclear arms race and, in particular, of its qualitative aspects. It could serve as an important measure for the non-proliferation of nuclear weapons, both vertical and horizontal. It would have a major arms limitation impact in that it would make it difficult, if not impossible, to develop new designs of nuclear weapons and would also place constraints on the modification of existing weapon designs. The permanent cessation of all nuclear-weapon tests has long been sought by the world community and its achievement would be an event of great international significance

Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part I : Physics and Nuclear Reactor

International Nuclear Information System (INIS)

Kusminarto; Sri Juari Santoso; Agus Taftazani; Sudjatmoko; Darsono; Samin; Syarip; Prajitno; Muhadi Ayub Wasitho; Sukarsono; Tjipto Sujitno; Elisabeth Supriyatni

2009-07-01

The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The proceedings contains papers presented on scientific meeting about Physics and Nuclear Reactor. The proceedings is the first part of the three parts which published in series. There are 28 papers. (PPIN)

A Teaching Method on Basic Chemistry for Freshman : Teaching Method with Pre-test and Post-test

OpenAIRE

立木, 次郎; 武井, 庚二

2003-01-01

This report deals with a teaching method on basic chemistry for freshman. This teaching method contains guidance and instruction to how to understand basic chemistry. Pre-test and post-test have been put into practice each time. Each test was returned to students at class in the following weeks.

Multi-Use seismic stations offer strong deterrent to clandestine nuclear weapons testing

Science.gov (United States)

Hennet, C. B.; Van der Vink, G. E.; Richards, P. G.; Adushkin, V. V.; Kopnichev, Y. F.; Geary, R.

As the United States and other nations push for the signing of a Comprehensive Test Ban Treaty, representatives are meeting in Geneva this year to develop an International Seismic Monitoring System to verify compliance with the treaty's restrictions. In addition to the official monitoring system, regional networks developed for earthquake studies and basic research can provide a strong deterrent against clandestine testing. The recent release of information by the U.S. Department of Energy (DoE) on previously unannounced nuclear tests provides an opportunity to assess the ability of multi-use seismic networks to help monitor nuclear testing across the globe.Here we look at the extent to which the formerly unannounced tests were recorded and identified on the basis of publicly available seismographic data recorded by five seismic networks. The data were recorded by networks in southern Nevada and northern California at stations less than 1500 km from the Nevada Test Site (NTS), and two networks in the former Soviet Union at stations farther than 1500 km from the NTS.

Basic research on nuclear track microfilters for gas separation

CERN Document Server

Sudowe, R; Ensinger, W; Vetter, J; Penzhorn, R D; Brandt, R

1999-01-01

Basic research on nuclear track microfilters, NTMF, made from the polyimide foil UPILEX, has been carried out to investigate the possible use of NTMF for gas separation in an environment containing large amounts of tritium. NTMF with a pore diameter as low as 0.1 mu m have been etched and metal replicas of the pores have been produced to determine the pore shape. An experimental setup for determining the separation factor of a NTMF for a given gas mixture has been constructed, and first experiments have been carried out.

EFFECT OF BASIC SKILLS IN ANY SITUATION TESTS ACCURACY YOUNG PLAYERS

Directory of Open Access Journals (Sweden)

Artan R. Kryeziu

2013-07-01

Full Text Available The paper aims to establish the impact of basic motor skills in some situational accuracy tests in youth basketball game. In a sample of 60 tested age of 17 year + / - 6 months. We have applied eigjt variables to the tested persons, five of which are predicting, while the other three are criterion tests. Connectivity between motor variables is handled through the correlation of Pearson. The impact of variables predicting in those criteria used in regression analysis. Also significant importance is given to the introduction of connectivity between basic motor skills in several accuracy tests typical for the basketball game situations. Regarding the basic motor skills variables have attained significant coherence, however situational space test throwing the ball in the basket in the same direction and shooting the ball in the basket in the corner 450 degres no coherence with any test has been shown from the space of the appility of basic motor skills. Through regression analysis procedure we’ve reviewed the impact of basic motor skills in some situational accuracy tests. Treat analysis of criterion variables in those predicting we can say that accuracy to situational variables impact junior league players had explosive force. Therefore we can conclude that explosive strength is a quite important factor in the game between young basketball players, with there moving actions the playes can achive their goal of scoring points.

Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Scientific and Technology Part II : Nuclear Chemistry; Process Technology and Radioactive Waste Management; Environment

International Nuclear Information System (INIS)

Sudjatmoko; Karmanto, Eko Edy; Endang-Supartini

1996-04-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity was held by Yogyakarta Nuclear Research Centre, National Atomic Energy Agency (BATAN) for monitoring the research activity which achieved in BATAN. The Proceeding contains a proposal about basic which has Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment. This proceeding is the second part from two part which published in series. There are 61 articles which have separated index

A basic study for development of environmental standard review plan of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

1999-12-15

In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

Statistics for nuclear engineers and scientists. Part 1. Basic statistical inference

Energy Technology Data Exchange (ETDEWEB)

Beggs, W.J.

1981-02-01

This report is intended for the use of engineers and scientists working in the nuclear industry, especially at the Bettis Atomic Power Laboratory. It serves as the basis for several Bettis in-house statistics courses. The objectives of the report are to introduce the reader to the language and concepts of statistics and to provide a basic set of techniques to apply to problems of the collection and analysis of data. Part 1 covers subjects of basic inference. The subjects include: descriptive statistics; probability; simple inference for normally distributed populations, and for non-normal populations as well; comparison of two populations; the analysis of variance; quality control procedures; and linear regression analysis.

Assessment of the current status of basic nuclear data compilations

International Nuclear Information System (INIS)

Riemer, R.L.

1992-01-01

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

The in-pile proving test for fuel assembly of Qinshan nuclear power plant

International Nuclear Information System (INIS)

Chen Dianshan; Zhang Shucheng; Kang Rixin; Wang Huarong; Chen Guanghan

1989-10-01

The in-pile proving test for fuel assembly of Qinshan nuclear power plant had been conducted in the experimental loop of HWRR at IAE (Institute of Atomic Energy) in Beijing, China, from January 1985 to December 1986. Average burnup of 27000 MWd/tU and peak burnup of 34000 MWd/tU of fuel rod had already been reached. The basic status of the experiment are described, emphasis is placed on the discussion of proving test parameters and analysis of experiment results

Nuclear test ban's last chance

International Nuclear Information System (INIS)

Barnaby, F.

1976-01-01

It is argued that if nuclear disarmament is the aim then some arms control treaties have been counterproductive. The two great powers have conducted, albeit underground, more nuclear explosions in the 12 years since the partial test ban than they did in the preceding 18 years, 1945 to 1963. The partial test ban treaty obliges the parties to negotiate a ban on 'all test explosions of nuclear weapons for all time'. After 12 years of negotiations very little progress has been made to this end. The USA and the USSR signed a bilateral Threshold Test Ban Treaty in 1974 banning 'any underground nuclear weapon tests having a yield exceeding 150 kilo-tons... beginning 31 March, 1976', a protocol describes how compliance is to be verified, and Article III requires that an agreement is to be negotiated governing peaceful nuclear explosions. From the point of view of disarmament it would be much better if the threshold test ban treaty were not ratified and a comprehensive test ban treaty were negotiated instead. The main official reason given for the failure to negotiate such a treaty is the problem of verification. However it is argued that due to recent progress in seismology there are no longer significant technical obstacles to the negotiation of a comprehensive test ban treaty. But there is lack of political will to obtain such a treaty. (U.K.)

A basic framework for managing time of nuclear plant projects

International Nuclear Information System (INIS)

Beck, J.R.

1987-01-01

One of the crucial problems that faces managers of nuclear power plant projects is how to obtain more effective and efficient utilization of their company's resources. Analysis of this problem showed that improvement was necessary in the time management area. Time management is one of the primary functions of project groups. Much has been written about planning and scheduling, and there are many modern techniques (CPM, PERT, etc.) available to a project group to manage time. So, why is time management still a problem? One reason is that nuclear projects are generally very complex and involve many organizations requiring the same resources. It is the intent of this paper to present a comprehensive and basic framework on which to either build a time management system or use as a basis to assess an existing system

Towards a nuclear-test ban

International Nuclear Information System (INIS)

1991-01-01

In 1986 and again in 1987 the General Assembly adopted resolutions by which it called on States conducting nuclear-test explosions to notify the Secretary-General, within one week of each explosion, of the time, place, yield and site characteristics of the test and also invited all other States to provide any such data on nuclear explosions that they might have. Over the years, in the Conference on Disarmament, members of the Group of 21 (mostly neutral and non-aligned countries) have continued to attach the utmost importance to the urgent conclusion of a comprehensive test-ban treaty as a significant contribution to the aim of ending the qualitative refinement of nuclear weapons and the development of new types of such weapons as well as of reversing the nuclear-arms race and achieving nuclear disarmament. In 1995 a conference will be convened to decide whether the non-proliferation Treaty will continue in force indefinitely, or will be extended for an additional fixed period or periods. Many States support the view that a comprehensive test ban would be a significant contribution to the non-proliferation of nuclear weapons; and some believe that, without a cessation of nuclear testing, it may not be possible to extend the NPT well beyond 1995. Other States, however, are of the opinion that the NPT, independently, offers benefits for the security of all States and, by its extension, will continue to do so

1989 basic plan for atomic energy development and utilization

International Nuclear Information System (INIS)

1989-01-01

A Basic Plan for Atomic Energy Development and Utilization has been established each year based on the guidelines set up by the Atomic Energy Commission of Japan, with the aim of promoting the development and utilization of atomic energy schematically and efficiently. The Basic Plan shows specific projects to achieve the objectives specified in the Long-Range Plan for Atomic Energy Development and Utilization. The Basic Plan specifies efforts to be made for overall strengthening of safety measures (safety policies, safety research, disaster prevention, etc.), promotion of nuclear power generation, establishment of the nuclear fuel cycle (securing of uranium, technology for uranium enrichment, reprocessing, etc.), development of new types of power reactors (fast breeder reactor, new types of converter reactors, plutonium fuel processing technology), promotion of leading projects (nuclear fusion, utilization of radiations, atomic powered ships, high-temperature engineering tests), promotion of basic technology development (basic research, training of scientists and engineers), voluntary and active international activities (international cooperation), and acquisition of understanding and cooperation of the general public. (N,K.)

Comprehensive Nuclear Test-ban Treaty

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The Comprehensive Nuclear Test-Ban Treaty was adopted by the General Assembly on 10 September 1996 (Res/50/245) and was open for signature by all states on 24 September 1996. It will enter into force 180 days after the date of deposit of the instruments of ratification by all states listed in Annex 2 to the Treaty. This document reproduces the text of the Treaty and the Protocol to the Comprehensive Nuclear Test-Ban Treaty Protocol to the Comprehensive Nuclear Test-Ban Treaty. 4 tabs.

Comprehensive Nuclear Test-ban Treaty

International Nuclear Information System (INIS)

1998-01-01

The Comprehensive Nuclear Test-Ban Treaty was adopted by the General Assembly on 10 September 1996 (Res/50/245) and was open for signature by all states on 24 September 1996. It will enter into force 180 days after the date of deposit of the instruments of ratification by all states listed in Annex 2 to the Treaty. This document reproduces the text of the Treaty and the Protocol to the Comprehensive Nuclear Test-Ban Treaty Protocol to the Comprehensive Nuclear Test-Ban Treaty

Technological progress and the Basic Law: Peaceful uses of nuclear energy

International Nuclear Information System (INIS)

Degenhart, C.

1983-01-01

The author explains that whereas the arguments put forward against the use of nuclear energy are largely based on our Basic Law, the opposite view, namely reasons speaking in favour of the peaceful use of nuclear energy, so far have not been given a comparably good footing of legitimation on constitutional grounds. He than proceeds in asking whether and how it is possible to find good reasons in our constitution to faster the peaceful use of nuclear energy, what effect this might have, and whether this is desirable for practical licensing work in accordance with the Atomic Energy Act. This question is important as problems of a general nature are currently discussed and decided within the framework of licensing procedures involving individual nuclear installations. As examples the author discusses the problem of determining the seriousness and type of risks on the basis of the constitution, or a general licence for certain types of industrial plants, the fundamental problem of waste management, but also questions of procedure or competence. (orig./HP) [de

Nuclear Test-Experimental Science

International Nuclear Information System (INIS)

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B.

1988-01-01

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program

The nuclear dissuasion without tests

International Nuclear Information System (INIS)

2003-02-01

Since the signature of the french treaty against the nuclear tests (Tice) in 1995, the french engineers must used the simulation to warrant the performance and the safety of weapons. This paper recalls the historical aspects of the french nuclear tests and presents the technological and scientific resources to simulate a nuclear weapon operating. a special interest is given to the computer TERA. (A.L.B.)

Nuclear tests and health: conference proceedings

International Nuclear Information System (INIS)

Beaudeau, M.C.

2002-01-01

This conference was organized by the observatory of French nuclear weapons - CDRPC-, the 'Moruroa e Tatou' association and the association of nuclear test veterans. Its aim was to call upon the victims of nuclear tests to speak about their health problems and to the possible consequences on their children's health. It pleads in favour of a particular legislation and in favour of the creation of an organization which would take for responsibility the health and environmental impacts of nuclear tests. (J.S.)

Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part I : Physics and Nuclear Reactor

International Nuclear Information System (INIS)

Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

2007-08-01

The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Physics and Nuclear Reactor and there are 52 papers. The proceedings is the first part of the three parts which published in series. (PPIN)

Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan

Directory of Open Access Journals (Sweden)

Bernd Grosche

2015-05-01

Full Text Available The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today’s radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose exposure and dosimetry, and evaluate new epidemiologic data and biological material collected from populations living in proximity to the test site. With time, new epidemiological data has been made available, and it is possible that these data may be linked to biological samples. Next to linking existing and newly available data to examine health effects, the existing dosimetry system needs to be expanded and further developed to include residential areas, which have not yet been taken into account. The aim of this paper is to provide an overview of previous studies evaluating the health effects of nuclear testing, including some information on dosimetry efforts, and pointing out directions for future epidemiologic studies.

Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan.

Science.gov (United States)

Grosche, Bernd; Zhunussova, Tamara; Apsalikov, Kazbek; Kesminiene, Ausrele

2015-01-01

The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today's radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose exposure and dosimetry, and evaluate new epidemiologic data and biological material collected from populations living in proximity to the test site. With time, new epidemiological data has been made available, and it is possible that these data may be linked to biological samples. Next to linking existing and newly available data to examine health effects, the existing dosimetry system needs to be expanded and further developed to include residential areas, which have not yet been taken into account. The aim of this paper is to provide an overview of previous studies evaluating the health effects of nuclear testing, including some information on dosimetry efforts, and pointing out directions for future epidemiologic studies.

Development and validation of a theoretical test in basic laparoscopy

DEFF Research Database (Denmark)

Strandbygaard, Jeanett; Maagaard, Mathilde; Larsen, Christian Rifbjerg

2013-01-01

for first-year residents in obstetrics and gynecology. This study therefore aimed to develop and validate a framework for a theoretical knowledge test, a multiple-choice test, in basic theory related to laparoscopy. METHODS: The content of the multiple-choice test was determined by conducting informal...... conversational interviews with experts in laparoscopy. The subsequent relevance of the test questions was evaluated using the Delphi method involving regional chief physicians. Construct validity was tested by comparing test results from three groups with expected different clinical competence and knowledge.......001). Internal consistency (Cronbach's alpha) was 0.82. There was no evidence of differential item functioning between the three groups tested. CONCLUSIONS: A newly developed knowledge test in basic laparoscopy proved to have content and construct validity. The formula for the development and validation...

The Wisconsin Test of Adult Basic Education (WITABE).

Science.gov (United States)

Pandey, Tej N.; Cleary, T. Anne

A description is given of "The Wisconsin Test of Adult Basic Education (WITABE)" which was developed specifically to measure the achievement of the individuals enrolled in the Rural Family Development (RGD) program at the University Extension, University of Wisconsin. The test is divided into three main parts or subtests: subtests 1 and…

Ground test facility for nuclear testing of space reactor subsystems

International Nuclear Information System (INIS)

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

1985-01-01

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

SPSS for applied sciences basic statistical testing

CERN Document Server

Davis, Cole

2013-01-01

This book offers a quick and basic guide to using SPSS and provides a general approach to solving problems using statistical tests. It is both comprehensive in terms of the tests covered and the applied settings it refers to, and yet is short and easy to understand. Whether you are a beginner or an intermediate level test user, this book will help you to analyse different types of data in applied settings. It will also give you the confidence to use other statistical software and to extend your expertise to more specific scientific settings as required.The author does not use mathematical form

The NPT and nuclear testing

International Nuclear Information System (INIS)

Howlett, D.; Simpson, J.

1992-01-01

One of the oldest unachieved aims of international nuclear disarmament and arms limitation negotiations is a Comprehensive Test Ban Treaty (CTBT). The history of the international negotiations, their outcomes and the consequences of Test Ban for the nuclear arsenals of the nuclear weapons states is discussed. The linkage between a CTBT and the Non-Proliferation Treaty is examined. Two strategies for moving towards a CTBT are compared; one a direct one, the other an incremental route. Both have several alternatives which are considered. (UK)

Can the deterrence survive to nuclear tests ban

International Nuclear Information System (INIS)

Gaffney, F.J. Jr.

1996-01-01

The problem of the soundness of the nuclear tests stopping is discussed here. The safety, the durability of nuclear weapons need nuclear tests. So, unless other means able to guarantee the deterrence, it is prejudicial to stop nuclear tests and to sign a non proliferation treaty with the option of zero nuclear explosion. (N.C.)

Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part II : Nuclear Chemistry and Process Technology

International Nuclear Information System (INIS)

Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

2007-08-01

The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Nuclear Chemistry and Process Technology and there are 47 papers which have separated index. The proceedings is the second part of the three parts which published in series. (PPIN)

Full scale dynamic testing of Paks nuclear power plant structures

International Nuclear Information System (INIS)

Da Rin, E.M.

1995-01-01

This report refers to the full-scale dynamic structural testing activities that have been performed in December 1994 at the Paks (H) Nuclear Power Plant, within the framework of: the IAEA Coordinated research Programme 'Benchmark Study for the Seismic Analysis and Testing of WWER-type Nuclear Power Plants, and the nuclear research activities of ENEL-WR/YDN, the Italian National Electricity Board in Rome. The specific objective of the conducted investigation was to obtain valid data on the dynamic behaviour of the plant's major constructions, under normal operating conditions, for enabling an assessment of their actual seismic safety to be made. As described in more detail hereafter, the Paks NPP site has been subjected to low level earthquake like ground shaking, through appropriately devised underground explosions, and the dynamic response of the plant's 1 st reactor unit important structures was appropriately measured and digitally recorded. In-situ free field response was measured concurrently and, moreover, site-specific geophysical and seismological data were simultaneously acquired too. The above-said experimental data is to provide basic information on the geophysical and seismological characteristics of the Paks NPP site, together with useful reference information on the true dynamic characteristics of its main structures and give some indications on the actual dynamic soil-structure interaction effects for the case of low level excitation

Evaluation of the basic concepts of approaches for the coexistence of nuclear energy and people/local community

International Nuclear Information System (INIS)

Kondo, Shunsuke; Kuroki, Shinichi; Nakagiri, Yuko

2007-01-01

In November 2007, the Policy Evaluation Committee compiled the report, which evaluated the basic concepts of approaches to the coexistence of nuclear energy and people/local community, specified in the Framework for Nuclear Energy Policy. The report states that the 'concerned administrative bodies are carrying out measures related to the coexistence of nuclear energy and people/local communities in line with these basic concept' and summarizes fifteen proposals conductive to the betterment and improvement of these measures, which were classified as 1) secure transparency and promotion of mutual understanding with the public, 2) development and enrichment of learning opportunities and public participation, 3) relationship between the government and local governments and 4) coexistence with local residents. The Japan Atomic Energy Commission (JAEC) considers this report to be reasonable. This article presented an overview of this activity. (T. Tanaka)

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

International Nuclear Information System (INIS)

Hicks, H.G.

1981-11-01

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

Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book I. Physics, Reactor Physics and Nuclear Instrumentation

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is part one from two books published for the meeting contains papers on Physics, Reactor Physics and Nuclear Instrumentation as results of research activities in National Atomic Energy Agency. There are 39 papers indexed individually. (ID)

Development of hot test equipment for advanced nuclear fuel cycle development in JNC

International Nuclear Information System (INIS)

Nomura, K.; Shibata, A.; Nemoto, S.; Aoshima, A.; Funasaka, H.

2001-01-01

JNC (Japan nuclear fuel cycle development institute) has been developing a mini centrifugal contactor. JNC has experience of the development of the RETF (Recycle equipment test facility; under construction at Tokai-works) type centrifugal contactor and the mini centrifugal contactor is designed on the basis of this knowledge. The followings were carried out in order to estimate the performance of the mini centrifugal contactor: functional test for evaluating basic performance of this extractor, acid-solvent test and uranium test for confirming that sufficient performance is attained. The results showed wide performance in comparison with the mini mixer settler used so far and it is expected that shortening in operating time and higher efficiency of extracting tests will be achieved. (author)

Assessment of IAEA safety series no. 75-INSAG-3 - ''basic safety principles for nuclear power plants''

International Nuclear Information System (INIS)

1989-01-01

The International Atomic Energy Agency Safety Series No. 75-INSAG--3, 'Basic Safety Principles for Nuclear Power Plants' is reviewed in the light of the Advisory Committee on Nuclear Safety reports ACNS--2, 'Safety Objectives for Nuclear Activities in Canada', and ACNS--4, 'Recommended General Safety Requirements for Nuclear Power Plants'. The INSAG safety objectives are consistent with the safety objectives stated in ACNS--2 but are less general, applying only to nuclear power plants. The INSAG safety principles are, in general, consistent with the requirements stated in ACNS--4 but put more emphasis on 'safety culture'. They give little attention to reactor plant effluents, waste management, or decommissioning. (fig., 5 refs.)

Basic characteristic test of buffer/backfill material under Horonobe groundwater condition

International Nuclear Information System (INIS)

Kikuchi, Hirohito; Tanai, Kenji

2005-02-01

By the second progress report (H12) on research and development for the geological disposal of high-level radioactive waste (HLW) in Japan, Japan Nuclear Cycle Development Institute (JNC) extended the data base of basic properties of compacted bentonite which were mainly obtained by using distilled water as test fluid. This report presents influence of Horonobe groundwater on the basic properties of buffer and backfill material. The Horonobe groundwater is a type of saline groundwater. The groundwater was sampled at GL-300 m or deeper by using bore hole HDB-6 of the underground laboratory of Horonobe site. In addition, basic properties are also obtained by using distilled water, synthetic seawater, and NaCl solution. Experimental results are as follows; 1) Swelling characteristics, hydraulic characteristics and mechanical characteristics of the buffer material and backfill material decrease by the influence of saline water. The relationship between effective clay density and swelling stress is described by the following equation. σ = exp (2.5786ρ b 3 - 12.238ρ b 2 + 21.818ρ b - 14.035) where σ is swelling stress [MPa], ρ b is effective clay density [Mg/m 3 ]. The relationship between effective clay density and intrinsic permeability is described by the following equation. κ = exp (-41.466 + 4.316ρ b - 4.069ρ b 2 ) where κ is intrinsic permeability [m 2 ], ρ b is effective clay density [Mg/m 3 ]. The relationship between effective clay density and unconfined compressive strength is described by the following equation. qu = 1.4 x 10 -4 exp (5.637ρ b ) where qu is unconfined compressive strength [MPa], ρ b is effective clay density [Mg/m 3 ]. 2) Saline water doesn't influence the thermal characteristic of the buffer material. The thermal conductivity and specific heat are derived by using the relationship that was obtained so far. (author)

Importance of tests in nuclear facilities

International Nuclear Information System (INIS)

Guillemard, B.

1985-10-01

In nuclear facilities, safety related systems and equipments are subject, along their whole service-life, to numerous tests. This paper analyses the role of tests in the successive stages of design, construction, exploitation of a nuclear facility. It examines several aspects of test quality control: definition of needs, test planning, intrinsic quality of each test, control of interfaces (test are both the end and the starting point of many actions concerned by quality) and the application [fr

Selected works of basic research on the physics and technology of accelerator driven clean nuclear power system

International Nuclear Information System (INIS)

Zhao Zhixiang

2002-01-01

38 theses are presented in this selected works of basic research on the physics and technology of accelerator driven clean nuclear power system. It includes reactor physics and experiment, accelerators physics and technology, nuclear physics, material research and partitioning. 13 abstracts, which has been presented on magazines home and abroad, are collected in the appendix

Assessment of the current status of basic nuclear data compilations

International Nuclear Information System (INIS)

1987-03-01

The Panel on Basic Nuclear Data Compilations believes that it is of paramount importance to achieve as short a cycle time as is reasonably possible in the evaluation and publication of the A-chains. The panel, therefore, has concentrated its efforts on identifying those factors that have tended to increase the cycle time and on finding ways to remove the obstacles. An important step was made during the past year to address reduction of the size of the published evaluations - another factor that can reduce cycle time. The Nuclear Structure and Decay Data (NSDD) network adopted new format guidelines, which generated a 30% reduction by eliminating redundancy and/or duplication. A current problem appears to be the rate at which the A-chains are being evaluated, which, on the average, is only about one-half of what it could be. It is hoped that the situation will improve with an increase in the number of foreign centers and an increase in efficiency as more A-chains are recycled by the same evaluator who did the previous evaluation. Progress has been made in the area of on-line access to the nuclear data files in that a subcommittee report describing the requirements of an on-line system has been produced. 2 tabs

The Indian nuclear test in a global perspective

International Nuclear Information System (INIS)

Subrahmanyam, K.

1974-01-01

A peaceful nuclear explosion test was carried out by India on 18 May, 1974 at Pokharan in the Rajasthan Desert. The test was carried out as a part of India's steady programme to develop nuclear energy for peaceful purposes and there was no diversion of resources from development as is charged by some nations. The test has broken the monopoly of the nuclear superpowers to conduct nuclear tests for which they are entiltled by the Non-proliferation Treaty (NPT) and at the same time, sharply focussed the attention on the discriminatory character of the NPT which does not allow non-nuclear states to carry out nuclear tests even for peaceful purposes. It is argued that India's going nuclear may prove, in the long run, beneficial to the cause of disarmament. (M.G.B.)

Survey of basic data on human resources development (HRD) in the nuclear field in FNCA countries (Contract research)

International Nuclear Information System (INIS)

2005-03-01

In the 3rd FNCA* (Forum for Nuclear Cooperation in Asia) Coordinator Meeting held on March 2002, it was proposed to carry out 'Survey of the Basic Data on Human Resources Development in the Nuclear Field'. It was considered to be the first step for developing the HRD strategy by producing the quantitative data on HRD in nuclear field. The survey results were introduced by Project Leaders during the 2002 FNCA Workshop on HRD held on October 2002. The follow-up survey was conducted with the cooperation of other Project Leaders in the respective field of FNCA such as medical and agriculture applications in each member countries. The collected survey data was analyzed in 2003, and summarized as 'Summary of the Survey Data'. This report consists of the summary of 'Survey of the Basic Data on Human Resources Development in Nuclear Field'. It was reported during the 2003 FNCA Workshop on HRD held on October 2003 and updated until early 2004. (author)

Proceedings of the Scientific Meeting and Presentation on Basic Researchin Nuclear Science and Technology part II: Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

International Nuclear Information System (INIS)

Sukarsono, R.; Karmanto, Eko-Edy; Suradjijo, Ganang

2000-01-01

Scientific Meeting and Presentation on Basic Research in Nuclear Scienceand Technology is an annual activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings. These are the second part of the proceedings that contain 71 articles in the fields of nuclear chemistry, process technology, radioactive waste management, and environment (PPIN).

Determination of the Basic Friction Angle of Rock Surfaces by Tilt Tests

Science.gov (United States)

Jang, Hyun-Sic; Zhang, Qing-Zhao; Kang, Seong-Seung; Jang, Bo-An

2018-04-01

Samples of Hwangdeung granite from Korea and Berea sandstone from USA, both containing sliding planes, were prepared by saw-cutting or polishing using either #100 or #600 grinding powders. Their basic friction angles were measured by direct shear testing, triaxial compression testing, and tilt testing. The direct shear tests and triaxial compression tests on the saw-cut, #100, and #600 surfaces indicated that the most reliable results were obtained from the #100 surface: basic friction angle of 29.4° for granite and 34.1° for sandstone. To examine the effect of surface conditions on the friction angle in tilt tests, the sliding angles were measured 50 times with two surface conditions (surfaces cleaned and not cleaned after each measurement). The initial sliding angles were high regardless of rock type and surface conditions and decreased exponentially as measurements continued. The characteristics of the sliding angles, differences between tilt tests, and dispersion between measurements in each test indicated that #100 surface produced the most reliable basic friction angle measurement. Without cleaning the surfaces, the average angles for granite (32 measurements) and sandstone (23 measurements) were similar to the basic friction angle. When 20-50 measurements without cleaning were averaged, the basic friction angle was within ± 2° for granite and ± 3° for sandstone. Sliding angles using five different tilting speeds were measured but the average was similar, indicating that tilting speed (between 0.2° and 1.6°/s) has little effect on the sliding angle. Sliding angles using four different sample sizes were measured with the best results obtained for samples larger than 8 × 8 cm.

SAFE testing nuclear rockets economically

International Nuclear Information System (INIS)

Howe, Steven D.; Travis, Bryan; Zerkle, David K.

2003-01-01

Several studies over the past few decades have recognized the need for advanced propulsion to explore the solar system. As early as the 1960s, Werner Von Braun and others recognized the need for a nuclear rocket for sending humans to Mars. The great distances, the intense radiation levels, and the physiological response to zero-gravity all supported the concept of using a nuclear rocket to decrease mission time. These same needs have been recognized in later studies, especially in the Space Exploration Initiative in 1989. One of the key questions that has arisen in later studies, however, is the ability to test a nuclear rocket engine in the current societal environment. Unlike the Rover/NERVA programs in the 1960s, the rocket exhaust can no longer be vented to the open atmosphere. As a consequence, previous studies have examined the feasibility of building a large-scale version of the Nuclear Furnace Scrubber that was demonstrated in 1971. We have investigated an alternative that would deposit the rocket exhaust along with any entrained fission products directly into the ground. The Subsurface Active Filtering of Exhaust, or SAFE, concept would allow variable sized engines to be tested for long times at a modest expense. A system overview, results of preliminary calculations, and cost estimates of proof of concept demonstrations are presented. The results indicate that a nuclear rocket could be tested at the Nevada Test Site for under $20 M

Development of nuclear technologies and conversion of nuclear weapon testing system infrastructure in Kazakhstan

International Nuclear Information System (INIS)

Cherepnin, Yu.; Takibaev, Zh.

2000-01-01

The article gives a brief description of the work done by the National Nuclear Center of the Republic of Kazakhstan in development of nuclear technology and conversion of nuclear weapon testing infrastructure in Kazakhstan. Content and trends of works are as follows: 1. Peaceful use of all physical facilities, created earlier for nuclear tests in Kazakhstan; 2. Development of methods and technologies for safe nuclear reactors use; 3. Examination of different materials in field of great neutron flow for thermonuclear reactor's first wall development; 4. Liquidation of all wells, which were formed in the results of underground nuclear explosions in Degelen mountain massif of former Semipalatinsk test site; 5. Study of consequences of nuclear tests in West Kazakhstan (territory of Azgir test site and Karachaganak oil field); 6. Study of radiological situation on the Semipalatinsk test site and surrounding territories; 7. Search of ways for high-level radioactive wastes disposal; 8. Construction of safe nuclear power plants in Kazakhstan

A study of existing experimental data and validation process for evaluated high energy nuclear data. Report of task force on integral test for JENDL High Energy File in Japanese Nuclear Data Committee

International Nuclear Information System (INIS)

Oyama, Yukio; Baba, Mamoru; Watanabe, Yukinobu

1998-11-01

JENDL High Energy File (JENDL-HE) is being produced by Japanese Nuclear Data Committee (JNDC) to provide common fundamental nuclear data in the intermediate energy region for many applications concerning a basic research, an accelerator-driven nuclear waste transmutation, a fusion material study, and medical applications like the radiation therapy. The first version of JENDL-HE, which contains the evaluated nuclear data up to 50 MeV, is planned to release in 1998. However, a method of integral test with which we can validate the high-energy nuclear data file has not been established. The validation of evaluated nuclear data through the integral tests is necessary to promote utilization of JENDL-HE. JNDC set up a task force in 1997 to discuss the problems concerning the integral tests of JENDL-HE. The task force members have surveyed and studied the current status of the problems for a year to obtain a guideline for development of the high-energy nuclear database. This report summarizes the results of the survey and study done by the task force for JNDC. (author)

Nuclear haematology

International Nuclear Information System (INIS)

Masjhur, J.S.

1992-01-01

Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used 32 P to treat chronic myeloid leukaemia and George Hevessy who used 32 P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

Monitoring of surface chemical and underground nuclear explosions with help of ionospheric radio-sounding above test site

International Nuclear Information System (INIS)

Krasnov, V.M.; Drobzheva, Ya.V.

2000-01-01

We describe the basic principles, advantages and disadvantages of ionospheric method to monitor surface chemical and underground nuclear explosions. The ionosphere is 'an apparatus' for the infra-sound measurements immediately above the test site. Using remote radio sounding of the ionosphere you can obtain that information. So you carry out the inspection at the test site. The main disadvantage of the ionospheric method is the necessity to sound the ionosphere with radio waves. (author)

Surface Disturbances at the Punggye-ri Nuclear Test Site: Another Indicator of Nuclear Testing?

Energy Technology Data Exchange (ETDEWEB)

Pabian, Frank V. [Los Alamos National Laboratory; Coblentz, David [Los Alamos National Laboratory

2017-02-03

A review of available very high-resolution commercial satellite imagery (bracketing the time of North Korea’s most recent underground nuclear test on 9 September 2016 at the Punggye-ri Underground Nuclear Test Site) has led to the detection and identification of several minor surface disturbances on the southern flank of Mt. Mantap. These surface disturbances occur in the form of small landslides, either alone or together with small zones of disturbed bare rock that appear to have been vertically lofted (“spalled”) as a result of the most recent underground explosion. Typically, spall can be uniquely attributed to underground nuclear testing and is not a result of natural processes. However, given the time gap of up to three months between images (pre- and post-event), which was coincident with a period of heavy typhoon flooding in the area1, it is not possible to determine whether the small landslides were exclusively explosion induced, the consequence of heavy rainfall erosion, or some combination of the two.

Basic plans on measures of mine site at the Ningyo-Toge Environmental Engineering Center

International Nuclear Information System (INIS)

2002-04-01

At the Ningyo-Toge and its peripheries, there are some mine relating facilities and apparatuses finishing their actions such as wasted stones and slags accumulation sites, and so on formed by results of searching and mining works of uranium mine carried out from beginning of 1950s by the Nuclear Fuels Corporation and the Power Reactor and Nuclear Fuel Development Corporation, both of which are predecessors of the Japan Nuclear Cycle Development Institute (JNC). These facilities are, at present, adequately maintained and managed by the Ningyo-Toge Environmental Engineering Center, but as resource development of uranium was positioned to a disposal business on JNC, JNC has investigated on optimal measuring methods and testing plans to evaluate their safety under cooperation with other works of JNC, to summarize a draft of the basic plans on measures of mine site'. Here were described two drafts of the 'Basic plans on measures of mine site' summarized on concepts and indications of whole of measures of mine relating facilities sites and of the 'Proof test plan' summarized on testing plans containing concrete measures to obtain basic data and knowledge required for progressing the measures and a proof test. (G.K.)

Guide related to structure sanitation in basic nuclear installations. Guide Nr 14, Release of the 30 August 2016

International Nuclear Information System (INIS)

2016-01-01

This guide defines recommendations made by the ASN regarding the sanitation methodology to be applied to buildings and structures of any basic nuclear installation. After a recall of the general doctrine for the management of wastes in basic nuclear installations, the guide presents the ASN doctrine for structure sanitation which distinguishes complete sanitation, extended sanitation, and sanitation in operation phase. It presents principles for the sanitation of component structures of an area of possible production of nuclear wastes. It indicates administrative procedures to be applied before and after sanitation works, notably when the radiological condition of structures has been made compatible or not with any use. After indication of requirements in terms of quality insurance, modalities of definition of defence lines (from first to fourth) are discussed. Requirements regarding the performance of sanitation operations are reviewed

India and the nuclear test ban

International Nuclear Information System (INIS)

Singh, J.

1998-01-01

India has sought a nuclear-test ban for the last 42 years bur is now unable to sign the Comprehensive Test ban Treaty (CTBT) when it is in its final form and moved to block its transmittal from the Conference on Disarmament to the UN General assembly. The negotiating mandate for the CTBT required it to effectively contribute to the process of disarmament. It is towards this end that India proposed amendments. Nuclear disarmament is fundamental for India's strategic and security interests. The only viable solution to India's security concerns related to nuclear weapons is in pursuing total elimination of nuclear weapons from national arsenals

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)

A history of US nuclear testing and its influence on nuclear thought, 1945-1963

CERN Document Server

Blades, David M

2014-01-01

As states continue to pursue nuclear weaponry, nuclear testing remains an important political issue in the twenty-first century. This survey examines how and why the U.S. conducted nuclear tests from 1945 through 1963 and the resulting influence on key questions from normalization and de-normalization up to the Nuclear Test Ban Treaty of 1963.

Australia - a nuclear weapons testing ground

International Nuclear Information System (INIS)

Dobbs, Michael.

1993-01-01

Between 1952 and 1958 Britain conducted five separate nuclear weapons trials in Australia. Australia had the uninhabited wide open spaces and the facilities which such tests need and Britain was able to use its special relationship with Australia to get agreement to conduct atomic tests in Australia and establish a permanent test site at Maralinga. Other non-nuclear tests were conducted between 1953-1963. The story of Britain's involvement in atomic weapons testing in Australia is told through its postal history. Both official and private covers are used to show how the postal communications were established and maintained throughout the test years. (UK)

Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

International Nuclear Information System (INIS)

Hayakawa, Masahiko

1981-01-01

The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

Nuclear energy and the nuclear energy industry

International Nuclear Information System (INIS)

Bromova, E.; Vargoncik, D.; Sovadina, M.

2013-01-01

A popular interactive multimedia publication on nuclear energy in Slovak. 'Nuclear energy and energy' is a modern electronic publication that through engaging interpretation, combined with a number of interactive elements, explains the basic principles and facts of the peaceful uses of nuclear energy. Operation of nuclear power plants, an important part of the energy resources of developed countries, is frequently discussed topic in different social groups. Especially important is truthful knowledgeability of the general public about the benefits of technical solutions, but also on the risks and safety measures throughout the nuclear industry. According to an online survey 'Nuclear energy and energy' is the most comprehensive electronic multimedia publication worldwide, dedicated to the popularization of nuclear energy. With easy to understand texts, interactive and rich collection of accessories stock it belongs to modern educational and informational titles of the present time. The basic explanatory text of the publication is accompanied by history and the present time of all Slovak nuclear installations, including stock photos. For readers are presented the various attractions legible for the interpretation, which help them in a visual way to make a more complete picture of the concerned issue. Each chapter ends with a test pad where the readers can test their knowledge. Whole explanatory text (72 multimedia pages, 81,000 words) is accompanied by a lot of stock of graphic materials. The publication also includes 336 photos in 60 thematic photo galleries, 45 stock charts and drawings, diagrams and interactive 31 videos and 3D models.

Decree 2805 by means of which the National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, is established

International Nuclear Information System (INIS)

1979-01-01

This Decree has for object to establish a National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, under the supervision of the National Council for the Nuclear Industry Development. Its aims are to account nuclear materials, to control nuclear activities, to preserve and control nuclear information, to keep technical relationship with specialized organizations, and to garant nuclear safeguards [es

Amendment of the atomic energy basic law and other related laws and establishment of the nuclear safety commission

International Nuclear Information System (INIS)

Ochi, Kenji

1978-01-01

The Atomic Energy Basic Law and related several laws were amended in the recent diet session. The amendment of the laws was requested after the radiation leakage from nuclear-powered ship ''Mutsu''. The reform of administrative system of atomic energy development and utilization are consisted of two important points: one is to establish the Nuclear Safety Commission for strengthening nuclear safety administration, and the other is to give an authority to each ministry or agency to regulate nuclear power reactor from the establishment to operation according to its original mission. (author)

Testing Basic Competency in Knee Arthroscopy Using a Virtual Reality Simulator

DEFF Research Database (Denmark)

Jacobsen, Mads Emil; Andersen, Morten Jon; Hansen, Claus Ol

2015-01-01

was set at a total z-score of 15.5 points, resulting in two of the novices passing the test and a single experienced surgeon failing the test. CONCLUSIONS: By combining four procedures on a virtual reality arthroscopy simulator, it was possible to create a valid, reliable, and feasible test of basic......BACKGROUND: Diagnostic knee arthroscopy is a common procedure that orthopaedic residents are expected to learn early in their training. Arthroscopy requires a different skill set from traditional open surgery, and many orthopaedic residents feel less prepared for arthroscopic procedures. Virtual...... reality simulation training and testing provide an opportunity to ensure basic competency before proceeding to supervised procedures in patients. METHODS: Twenty-six physicians (thirteen novices and thirteen experienced arthroscopic surgeons) were voluntarily recruited to perform a test consisting of five...

Nuclear haematology

Energy Technology Data Exchange (ETDEWEB)

Masjhur, J S

1993-12-31

Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used {sup 32}P to treat chronic myeloid leukaemia and George Hevessy who used {sup 32}P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

Database on radioecological situation in Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

1999-01-01

One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

Nuclear system test simulator

International Nuclear Information System (INIS)

Sawyer, S.D.; Hill, W.D.; Wilson, P.A.; Steiner, W.M.

1987-01-01

A transportable test simulator is described for a nuclear power plant. The nuclear power plant includes a control panel, a reactor having actuated rods for moving into and out of a reactor for causing the plant to operate, and a control rod network extending between the control panel and the reactor rods. The network serially transmits command words between the panel and rods, and has connecting interfaces at preselected points remote from the control panel between the control panel and rods. The test simulator comprises: a test simulator input for transport to and connection into the network at at least one interface for receiving the serial command words from the network. Each serial command includes an identifier portion and a command portion; means for processing interior of the simulator for the serial command words for identifying that portion of the power plant designated in the identifier portion and processing the word responsive to the command portion of the word after the identification; means for generating a response word responsive to the command portion; and output means for sending and transmitting the response word to the nuclear power plant at the interface whereby the control panel responds to the response word

Perception of basic tastes and threshold sensitivity during testing of selected judges

Directory of Open Access Journals (Sweden)

Peter Zajác

Full Text Available Normal 0 false false false SK JA X-NONE The sense of taste is one of the most important human senses. Alteration in taste perception can greately interfere to our lives, because it influences our dietary habits and consequently general human health. Many physiological and external factors can cause the loss of taste perception. These factors include for example certain diseases, the side effect of the use of certain medicaments, head trauma, gender, dietary habbits, smoking, role of saliva, age, stress and many more. In this paper we are discussing perception of basic tastes and treshold sensitivity during testing of selected groupe of 500 sensory judges. A resolution taste test and sensitivity treshold test were performed using basic tastes (sour, bitter, salty, sweet, umami, astringent, metallic. We have found that the perception of basic tastes decreese with human age. Smoking leads to significant errors in the determination of basic tastes. Different mistakes occures in different age categories. This study suggests further researches, investigating various factors influencing taste perception.  doi:10.5219/259

Status of the flora and fauna on the Nevada Test Site, 1993. Results of continuing basic environmental monitoring, January through December 1993

International Nuclear Information System (INIS)

Hunter, R.B.

1994-09-01

This report provides the results of monitoring of plants and animals on the Nevada Test Site during calendar year 1993. Monitoring was accomplished under the Department of Energy's Basic Environmental Compliance and Monitoring Program, initiated in 1987. The program looks at both baseline study areas, chosen to represent undisturbed conditions as much as possible, and areas disturbed by Department of energy (DOE) activities or natural phenomena. DOE disturbances studied include areas blasted by above-ground nuclear tests before 1962, subsidence craters created by underground nuclear tests, road maintenance activities, areas cleared for drilling, and influences of man-made water sources. Natural phenomena studied include recovery from range fires, effects of introduced species, damage to plants by insect outbreaks, and effects of weather fluctuations. In 1993 disturbances examined included several burned areas and roadsides, a drill pad on Pahute Mesa, introduced grasses and shrub removal effects on ephemeral plants, and effects on pine trees of an infestation of pinyon needle scale insects

Status of the flora and fauna on the Nevada Test Site, 1993. Results of continuing basic environmental monitoring, January through December 1993

Energy Technology Data Exchange (ETDEWEB)

Hunter, R.B. [comp.

1994-09-01

This report provides the results of monitoring of plants and animals on the Nevada Test Site during calendar year 1993. Monitoring was accomplished under the Department of Energy`s Basic Environmental Compliance and Monitoring Program, initiated in 1987. The program looks at both baseline study areas, chosen to represent undisturbed conditions as much as possible, and areas disturbed by Department of energy (DOE) activities or natural phenomena. DOE disturbances studied include areas blasted by above-ground nuclear tests before 1962, subsidence craters created by underground nuclear tests, road maintenance activities, areas cleared for drilling, and influences of man-made water sources. Natural phenomena studied include recovery from range fires, effects of introduced species, damage to plants by insect outbreaks, and effects of weather fluctuations. In 1993 disturbances examined included several burned areas and roadsides, a drill pad on Pahute Mesa, introduced grasses and shrub removal effects on ephemeral plants, and effects on pine trees of an infestation of pinyon needle scale insects.

The Basic Framework for Robot Applicability Enhancement of Nuclear Risk Management in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Choi, Young; Jeong, Kungmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Inn Seock [bISSA Technology, Inc., Germantown (United States)

2015-05-15

Beyond-design-basis external events such as the one having occurred at the Fukushima Daiichi Nuclear Power Plant typically pose considerable challenges to the plant personnel because of the harsh environments caused by the events (e.g., extreme terrains, high radiation, radioactive rubbles, high heat, and explosive environment). Therefore, remote response techniques by use of robotic systems are needed to help the plant personnel cope with the extreme events. In this study the basic framework for enhancing robotic applicability to disaster management was developed using the analytic technique of Master Logic Diagram (MLD) and Goal-Tree Success-Tree (GTST). The users of robots have to devise a sound maintenance program, otherwise their unscheduled downtime may increase beyond limit, consequently defeating the purpose of robot applications. In addition, maintainability could be enhanced by designing for ease of diagnosis, and ease of access and repair. Ways to upgrade maintainability could be devised by evaluating maintainability in the design stage. The basic framework discussed herein shall be used by the KAERI's robotics team as a fundamental framework in enhancing the applicability of disaster robots in the hazardous environment caused by extreme events.

Verifying seismic design of nuclear reactors by testing. Volume 1: test plan

Energy Technology Data Exchange (ETDEWEB)

1979-07-20

This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program.

Verifying seismic design of nuclear reactors by testing. Volume 1: test plan

International Nuclear Information System (INIS)

1979-01-01

This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program

Verification methods for treaties limiting and banning nuclear tests

International Nuclear Information System (INIS)

Voloshin, N.P.

1998-01-01

Treaty on limitation of underground nuclear weapon tests and treaty on world banning of nuclear tests contribute to and accompany the process of nuclear disarmament. Test ban in three (Moscow treaty of 1963) as well as the Threshold Test Ban up to 1991 was controlled only with national means. But since 1991 nuclear test threshold of 150 kt has been measured with hydrodynamic and tele seismic methods and checked by the inspection. Distinctive feature of this control is that control is that it is bilateral. This conforms to Treaty on limitation of underground nuclear weapon tests signed by two countries - USA and USSR. The inspection at the place of tests requires monitoring of the test site of the party conducting a test and geological information of rock in the area of explosion. In the treaty of the World Nuclear Test Ban the following ways of international control are provided for: - seismologic measurements; - radionuclide measurements; - hydro-acoustics measurements; - infra-sound measurements; - inspection at the place of the tests conduction

The Creation of a French Basic Nuclear Installation - Description of the Regulatory Process - 13293

Energy Technology Data Exchange (ETDEWEB)

Mahe, Carole [CEA Marcoule - BP17171 - 30207 Bagnols-Sur-Ceze (France); Leroy, Christine [CEA Cadarache - 13108 Saint Paul-Lez-Durance (France)

2013-07-01

CEA is a French government-funded technological research organization. It has to build a medium-level waste interim storage facility because the geological repository will not be available until 2025. This interim storage facility, called DIADEM, has to be available in 2017. These wastes are coming from the research facilities for spent fuel reprocessing and the dismantling of the most radioactive parts of nuclear facilities. The CEA handles the waste management by inventorying the needs and updating them regularly. The conception of the facility is mainly based on this inventory. It provides quantity and characteristics of wastes and it gives the production schedule until 2035. Beyond mass and volume, main characteristics of these radioactive wastes are chemical nature, radioisotopes, radioactivity, radiation dose, the heat emitted, corrosive or explosive gas production, etc. These characteristics provide information to study the repository safety. DIADEM mainly consists of a concrete cell, isolated from the outside, wherein stainless steel welded containers are stored, stacked in a vertical position in the racks. DIADEM is scheduled to store three types of 8 mm-thick, stainless steel cylindrical containers with an outside diameter 498 mm and height from 620 to 2120 mm. DIADEM will be a basic nuclear installation (INB in French) because of overall activity of radioactive substances stored. The creation of a French basic nuclear installation is subject to authorization according to the French law No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field. The authorization takes into account the technical and financial capacities of the licensee which must allow him to conduct his project in compliance with these interests, especially to cover the costs of decommissioning the installation and conduct remediation work, and to monitor and maintain its location site or, for radioactive waste disposal installations, to cover the definitive shut

The Creation of a French Basic Nuclear Installation - Description of the Regulatory Process - 13293

International Nuclear Information System (INIS)

Mahe, Carole; Leroy, Christine

2013-01-01

CEA is a French government-funded technological research organization. It has to build a medium-level waste interim storage facility because the geological repository will not be available until 2025. This interim storage facility, called DIADEM, has to be available in 2017. These wastes are coming from the research facilities for spent fuel reprocessing and the dismantling of the most radioactive parts of nuclear facilities. The CEA handles the waste management by inventorying the needs and updating them regularly. The conception of the facility is mainly based on this inventory. It provides quantity and characteristics of wastes and it gives the production schedule until 2035. Beyond mass and volume, main characteristics of these radioactive wastes are chemical nature, radioisotopes, radioactivity, radiation dose, the heat emitted, corrosive or explosive gas production, etc. These characteristics provide information to study the repository safety. DIADEM mainly consists of a concrete cell, isolated from the outside, wherein stainless steel welded containers are stored, stacked in a vertical position in the racks. DIADEM is scheduled to store three types of 8 mm-thick, stainless steel cylindrical containers with an outside diameter 498 mm and height from 620 to 2120 mm. DIADEM will be a basic nuclear installation (INB in French) because of overall activity of radioactive substances stored. The creation of a French basic nuclear installation is subject to authorization according to the French law No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field. The authorization takes into account the technical and financial capacities of the licensee which must allow him to conduct his project in compliance with these interests, especially to cover the costs of decommissioning the installation and conduct remediation work, and to monitor and maintain its location site or, for radioactive waste disposal installations, to cover the definitive shut

Basic professional training course on nuclear safety - Finland YK4 preface

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

2006-01-01

This publication comprises the abstracts of the YK4 basic professional training course on nuclear safety arranged now for fourth time in Finland. Part of the abstracts has again been updated for this publication. When more renewed abstracts are received during the YK4 course, they are put in the distance learning pages of Lappeenranta University of Technology (LUT) being thus immediately available for the participants. In the fall of 2002, Finnish organizations re-evaluated the man-power situation and established an organizing committee to develop and organize basic post-graduate professional training of new recruits and staff members; especially for the acute needs of the new NPP project, but also to provide in the long-term a new generation of nuclear experts to replace the present generation which will retire within the next ten years. The organizing committee included representatives of the following organizations: Radiation and Nuclear Safety Authority STUK, nuclear power utilities TVO and Fortum, the Technical Research Centre of Finland VTT, the Lappeenranta (LUT) and Helsinki Universities of Technology (TKK), and the Ministry of Trade and Industry, KTM. The committee decided to promptly organize a national training course on nuclear safety based on a similar course developed by the IAEA: the course structure and syllabus are alike. Although part of the course material is based on the IAEA material, it has been adapted to the Finnish conditions, and a large part of the material is completely new. The Finnish application aims to make visible different standpoints of all organizations and the location of the five-week course rotates between different organizations. In the academic year 2006-2007, the course is starting fourth time as YK4. There are again over 100 lecturers and rehearsal, demonstration or excursion leaders. Half of them come from the utilities TVO and Fortum, a quarter from the authority STUK, and the rest from VTT, universities and others. The

Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book II. Nuclear Chemistry, Process Technology, and Radioactive Waste Processing and Environment

International Nuclear Information System (INIS)

1996-06-01

The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is second part of two books published for the meeting contains papers on nuclear chemistry, process technology, and radioactive waste management and environment. There are 62 papers indexed individually. (ID)

Basic elements of nuclear geophysics

International Nuclear Information System (INIS)

Nordemann, D.J.R.; Pereira, E.B.

1984-01-01

Nuclear Geophysics applies the nuclear radiation detection methodology to the geosciences, specially to study the dynamical processes of the lithosphere, the hydrosphere and the atmosphere as well as some aspects of planetology and astrophysics. Here the main methods are described: alpha-ray and gamma-ray spectrometry, the interaction of alpha and gamma radiation with matter and the detectors used (grid chambers, surface barrier silicon detector for alpha radiation; and sodium iodide thallium activated phosphors, hyperpure and lithium drifted germanium semiconductor detectors for gamma radiation). The principal applications of Nuclear Geophysics are given as examples to ilustrate the use of the methods described. (AUthor) [pt

A portable meteorological station plus nuclear radiation monitoring system using a basic-8052 micro-controller

International Nuclear Information System (INIS)

Al-Mohamad, A.; Aghabi, S.; Weiss, C.

2002-01-01

a portable meteorology station capable of measuring various atmospheric parameters (mainly ambient temperature, relative humidity, atmospheric pressure, wind speed and direction) was designed and built. The physical quantities were converted to electrical signals using suitable sensors. These signals were then processed and transferred to digital values to be stored in suitable memories. A nuclear radiation alarm system was also built, on the main board, to monitor the nuclear radiation releases levels. The system consists of three main parts: control board, data acquisition board and signals conditioning board. the overall system is controlled by a BASIC-8052 micro-controller. (authors)

Teaching and testing basic surgical skills without using patients

Directory of Open Access Journals (Sweden)

Razavi M

2004-10-01

Full Text Available Background: Nowadays, clinical skills centers are important structural components of authentic universities in the world. These centers can be use for tuition of cognitive, affective and psychomotor skills. In this study we have designed a surgical course, consist of 19 theoretical knowledge (cognitive skills and 10 procedural skills. Purpose: teaching and testing the designed course. Methods: This study has been conducted on 678 medical students at clerkship stage. Pre and post-self assessment technique has been used to assess learning progress. A multivariate statistical comparison were adapted for Judgments of learning achievement, Hotelling’s T-square has been used to ascertain the differences between pre and post tests score. For measuring the reliability of the test items. Cronbach's Alpha has been used to measure the reliability of test item. Results: The reliability of the test was 0.84 for cognitive skills and 0.92 for procedural skills. The two tailed test for comparing each pairs of score of 19 cognitive items showed a significant statistical difference between 13 items (P=0.000. For procedural skills the differences between the mean score of 9 items were significant (P=0.000. These results indicate learning achievements by students. Conclusion: This study suggests that, the ability of trainees in both cognitive and psychomotor skills can be improved by tuition of basic surgical skills in skill Lab. (without use of patients. Key words: BASIC SURGICAL SKILLS, CSC, (CLINICAL SKILLS CENTER PRE AND POST SELF-ASSESSMENT

IEEE standard criteria for type tests of class 1E modules used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1977-01-01

The Institute of Electrical and Electronics Engineers has generated this document to provide direction for type testing Class 1E modules and obtaining specific type test data. It supplements IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for Class 1E equipment qualification. Adherence to this document alone may not suffice for assuring public health and safety because it is the integrated performance of the structures, the fluid systems, the electrical systems, the instrumentation systems of the station, and in particular, the plant protection system of which these modules are a part that prevents accidents or limits the consequences of accidents. Each applicant to the Nuclear Regulatory Commission for a license to operate a nuclear power generating station has the responsibility to assure himself and others that this document, if used, is pertinent to his application and that the integrated performance of his station is adequate

Proceeding on the scientific meeting and presentation on basic research of nuclear science and technology (book I): physics, reactors

International Nuclear Information System (INIS)

Syarip; Prayitno; Samin; Agus Taftazani; Sudjatmoko; Pramudita Anggraita; Gede Sutresna W; Tjipto Sujitno; Slamet Santosa; Herry Poernomo; R Sukarsono; Prajitno

2014-06-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is an annual activity held by Centre for Accelerator Science and Technology, National Nuclear Energy Agency, in Yogyakarta, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings which were divided into two groups that are physics and nuclear reactors. The proceedings consists of three articles from keynote speakers and 25 articles from BATAN and others participants.(PPIKSN)

Basic principles of test-negative design in evaluating influenza vaccine effectiveness.

Science.gov (United States)

Fukushima, Wakaba; Hirota, Yoshio

2017-08-24

Based on the unique characteristics of influenza, the concept of "monitoring" influenza vaccine effectiveness (VE) across the seasons using the same observational study design has been developed. In recent years, there has been a growing number of influenza VE reports using the test-negative design, which can minimize both misclassification of diseases and confounding by health care-seeking behavior. Although the test-negative designs offer considerable advantages, there are some concerns that widespread use of the test-negative design without knowledge of the basic principles of epidemiology could produce invalid findings. In this article, we briefly review the basic concepts of the test-negative design with respect to classic study design such as cohort studies or case-control studies. We also mention selection bias, which may be of concern in some countries where rapid diagnostic testing is frequently used in routine clinical practices, as in Japan. Copyright © 2017. Published by Elsevier Ltd.

Basic concept of the nuclear emergency preparedness and response in Japan after the accident of the Fukushima Dai-ichi Nuclear Power Station. The plain explanation for regional officials and emergency workers

International Nuclear Information System (INIS)

Sato, Sohei; Yamamoto, Kazuya

2013-07-01

After the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station occurred on March 11, 2011, actions for controlling the accident and protective actions for the residents like evacuation were taken. In parallel with this, it has been developed to reform the nuclear regulatory systems and the emergency preparedness and response systems in Japan. Especially the Nuclear Regulation Authority's Nuclear Emergency Preparedness and Response Guidelines were adopted with the introducing the basic concepts and the criteria on the basis of the IAEA's safety standards and differed greatly from the prior guidelines. Thus the arrangement of emergency response systems, resources and the operational procedures will be developed complying with according to the guidelines in municipalities around the nuclear power station sites. This work attempts to provide a plain explanation as possible for the regional officials and emergency workers about the basic concepts of the new guidelines. (author)

Soviet nuclear testing: The Republics say no

International Nuclear Information System (INIS)

Carter, L.J.

1990-01-01

Massive protests are taking place in Russia against nuclear weapons testing. Efforts have been mounted to stop all testing at Kazakhstan test site near the town of Semipalatinsk, site of the first nuclear detonation in 1949 and of more than 500 test conducted since. Boris Yeltsin proposed just after his election as president of the federation the elimination of testing grounds for nuclear and biological weapons on Russian territory. The central government in Moscow has announced that it is considering closing the Semipalatinsk site. Reaction has also been strong to testing at the Arctic island of Novaya Zemlya, and severe constraints, such as Arctic cold, frozen rocks, high winds, difficult access, and protests by Greenpeace activists and USSR's Nordic neighbors do not make this site attractive. The author feels that this movement in the USSR has set in motion a politically dynamic situation that makes for the best chance for a comprehensive test ban treaty yet witnessed

Testing of adsorbents used in nuclear power plant air cleaning systems using the open-quotes Newclose quotes standards

International Nuclear Information System (INIS)

Freeman, W.P.

1993-01-01

Ever since the publication of the NRC Information Notice No. 87-32: Deficiencies in the Testing of Nuclear-Grade Activated Charcoal, nuclear power facilities in the US have struggled in their efforts to open-quotes...review the information for applicability to their facilities and consider action, if appropriate ...close quotes as stated in the notice. The encouragement of resident NRC inspectors at some nuclear power facilities has prompted a variety of responses ranging from no change at all in testing requirements to contemplated changes in plant technical specifications. This confusion is the result of a couple factors. The first factor is the lack of a current revision to NRC Regulatory Guide 1.52, the basic document used in nuclear power plant technical specifications for the testing of engineered-safety feature (ESF) post accident air cleaning systems. The second factor is the standards that have been written since the last revision of Reg. Guide 1.52 which include two revision of ANSI N509 and N510, two revisions of RDT M16-1T, two version of ASTM D3803, two versions of ASTM D4069, and three versions of an SME code AG-1. Few of the standards and codes listed above are commensurate with each other and, thus, present a nearly insolvable maze to the HVAC engineer asked to upgrade adsorbent testing requirements following the standards. This paper describes the authors experience with a number of nuclear power facilities in their efforts to meet the requirements of the new standards of testing adsorbents from nuclear power plant air cleaning systems. The existing standards are discussed in light of the current state of the art for adsorbent testing of adsorbent media from nuclear air treatment systems. Test results are presented showing the impact of new test requirements on acceptance criteria when compared to the old test requirements and recommendations are offered for solution of this testing problem in the future. 12 refs., 5 tabs

Analysis of North Korea's Nuclear Tests under Prospect Theory

International Nuclear Information System (INIS)

Lee, Han Myung; Ryu, Jae Soo; Lee, Kwang Seok; Lee, Dong Hoon; Jun, Eunju; Kim, Mi Jin

2013-01-01

North Korea has chosen nuclear weapons as the means to protect its sovereignty. Despite international society's endeavors and sanctions to encourage North Korea to abandon its nuclear ambition, North Korea has repeatedly conducted nuclear testing. In this paper, the reason for North Korea's addiction to a nuclear arsenal is addressed within the framework of cognitive psychology. The prospect theory addresses an epistemological approach usually overlooked in rational choice theories. It provides useful implications why North Korea, being under a crisis situation has thrown out a stable choice but taken on a risky one such as nuclear testing. Under the viewpoint of prospect theory, nuclear tests by North Korea can be understood as follows: The first nuclear test in 2006 is seen as a trial to escape from loss areas such as financial sanctions and regime threats; the second test in 2009 was interpreted as a consequence of the strategy to recover losses by making a direct confrontation against the United States; and the third test in 2013 was understood as an attempt to strengthen internal solidarity after Kim Jong-eun inherited the dynasty, as well as to enhance bargaining power against the United States. Thus, it can be summarized that Pyongyang repeated its nuclear tests to escape from a negative domain and to settle into a positive one. In addition, in the future, North Korea may not be willing to readily give up its nuclear capabilities to ensure the survival of its own regime

Test facilities for evaluating nuclear thermal propulsion systems

International Nuclear Information System (INIS)

Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C.; Todosow, M.

1992-01-01

Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized

Nuclear energy: basics, present, future

Directory of Open Access Journals (Sweden)

Ricotti M. E

2013-06-01

Full Text Available The contribution is conceived for non-nuclear experts, intended as a synthetic and simplified overview of the technology related to energy by nuclear fission. At the end of the paper, the Reader will find a minimal set of references, several of them on internet, useful to start deepening the knowledge on this challenging, complex, debated albeit engaging energy source.

Current challenges for education of nuclear engineers. Beyond nuclear basics

Energy Technology Data Exchange (ETDEWEB)

Schoenfelder, Christian [AREVA GmbH, Offenbach (Germany). Training Center

2014-07-15

In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

Current challenges for education of nuclear engineers. Beyond nuclear basics

International Nuclear Information System (INIS)

Schoenfelder, Christian

2014-01-01

In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

The role of inertial containment fusion in replacing nuclear tests

Energy Technology Data Exchange (ETDEWEB)

Schaper, Annette [Hessische Stiftung Friedens- und Konfliktforschung, Frankfurt am Main (Germany)

2008-07-01

Nuclear weapon physicists need to understand the process of a nuclear explosion, and their major experimental tools had been nuclear tests. Since a couple of years, the established nuclear weapon states observe a testing moratorium. Nevertheless, they still want to keep their nuclear arsenals, and consequently to ensure the reliability, safety, and security of their nuclear warheads. For this purpose, they use experimental tools that replace nuclear tests, among them ICF. ICF plays a central role in the so-called ''stockpile stewardship program'' that the U.S. has implemented when it participated in the negotiations on a Comprehensive Test Ban Treaty. Several questions arise and are discussed in the presentation: Does ICF allow to simulate the extreme conditions of a nuclear explosion? Which are the functions of nuclear testing that ICF can replace and which are beyond its capabilities? Would ICF be a useful tool for the design of new nuclear warheads? Why are so huge sums spent on ICF in a military context although the usefulness for nuclear weapons seems rather limited?.

Basic Testing of the DUCHAMP Source Finder

Science.gov (United States)

Westmeier, T.; Popping, A.; Serra, P.

2012-01-01

This paper presents and discusses the results of basic source finding tests in three dimensions (using spectroscopic data cubes) with DUCHAMP, the standard source finder for the Australian Square Kilometre Array Pathfinder. For this purpose, we generated different sets of unresolved and extended Hi model sources. These models were then fed into DUCHAMP, using a range of different parameters and methods provided by the software. The main aim of the tests was to study the performance of DUCHAMP on sources with different parameters and morphologies and assess the accuracy of DUCHAMP's source parametrisation. Overall, we find DUCHAMP to be a powerful source finder capable of reliably detecting sources down to low signal-to-noise ratios and accurately measuring their position and velocity. In the presence of noise in the data, DUCHAMP's measurements of basic source parameters, such as spectral line width and integrated flux, are affected by systematic errors. These errors are a consequence of the effect of noise on the specific algorithms used by DUCHAMP for measuring source parameters in combination with the fact that the software only takes into account pixels above a given flux threshold and hence misses part of the flux. In scientific applications of DUCHAMP these systematic errors would have to be corrected for. Alternatively, DUCHAMP could be used as a source finder only, and source parametrisation could be done in a second step using more sophisticated parametrisation algorithms.

Basic nucleonics. 2. ed.

International Nuclear Information System (INIS)

Guzman, M.E.

1989-01-01

This book is oriented mainly towards professionals who are not physicists or experts in nuclear sciences, physicians planning to specialize in nuclear medicine or radiotherapy and technicians involved in nuclear applications. The book covers the fundamental concepts of nuclear science and technology in a simple and ordered fashion. Theory is illustrated with appropriate exercises and answers. With 17 chapters plus 3 appendices on mathematics, basic concepts are covered in: nuclear science, radioactivity, radiation and matter, nuclear reactions, X rays, shielding and radioprotection

Guide to the declaration procedure and coding system for criteria concerning significant events related to safety, radiation protection or the environment, applicable to basic nuclear installations and the transport of radioactive materials

International Nuclear Information System (INIS)

Lacoste, Andre-Claude

2005-01-01

This guide notably contains various forms associated with the declaration of significant events, and explanations to fill them in: significant event declaration form for a basic nuclear installation, significant event declaration form for radioactive material transport, significant event report for a basic nuclear installation, significant event report for radioactive material transport, declaration criteria for significant events related to the safety of non-PWR basic nuclear installations, declaration criteria for significant events related to PWR safety, significant events declared further to events resulting in group 1 unavailability and non-compliance with technical operating specifications, declaration criteria for significant events concerning radiation protection for basic nuclear installations, declaration criteria for significant events concerning environmental protection, applicable to basic nuclear installations, and declaration criteria for significant events concerning radioactive material transport

Interpreting Mathematics Scores on the New Jersey College Basic Skills Placement Test.

Science.gov (United States)

Dass, Jane; Pine, Charles

The New Jersey College Basic Skills Placement Test (NJCBSPT) is designed to measure certain basic language and mathematics skills of students entering New Jersey colleges. The primary purpose of the two mathematics sections is to determine whether students are prepared to begin certain college-level work without a handicap in computation or…

Further limitations on nuclear testing

International Nuclear Information System (INIS)

Brown, P.S.

1991-11-01

This document addresses a number of subjects related to further constraints on nuclear testing, briefly discussing each of the following topics: the current political situation, the kinds of steps that might next be taken in test limitations and the impacts of further testing limits, the need for a test ban readiness program, some issues related to verification, and the possibility of confidence building measures as alternative, or near-term, steps to further test limitations

French nuclear plant safeguard pump qualification testing: EPEC test loop

International Nuclear Information System (INIS)

Guesnon, H.

1985-01-01

This paper reviews the specifications to which nuclear power plant safeguard pumps must be qualified, and surveys the qualification methods and program used in France to verify operability of the pump assembly and major pump components. The EPEC test loop is described along with loop capabilities and acheivements up to now. This paper shows, through an example, the Medium Pressure Safety Injection Pump designed for service in 1300 MW nuclear power plants, and the interesting possibilities offered by qualification testing

Xenon monitoring and the Comprehensive Nuclear-Test-Ban Treaty

Energy Technology Data Exchange (ETDEWEB)

Bowyer, Theodore W. [Nuclear Explosion Monitoring Program, Pacific Northwest National Laboratory, Richland, Washington 99352 (United States)

2014-05-09

How do you monitor (verify) a CTBT? It is a difficult challenge to monitor the entire world for nuclear tests, regardless of size. Nuclear tests 'normally' occur underground, above ground or underwater. Setting aside very small tests (let's limit our thinking to 1 kiloton or more), nuclear tests shake the ground, emit large amounts of radioactivity, and make loud noises if in the atmosphere (or hydroacoustic waves if underwater)

Safety of Basic nuclear facilities (INB) other than electronuclear reactors. Lessons learned from declared significant events in 2011 and 2012

International Nuclear Information System (INIS)

2013-01-01

The first part of this report presents the different types of basic nuclear facilities other than electronuclear reactors. These installations can be industrial installations dedicated or not to the nuclear fuel cycle, research and support installations, be definitively stopped or being dismantled, or radioactive waste storage installations. After a comment of the main trends noticed in 2011 and 2012, the report proposes a transverse analysis of events which occurred in these installations. These events are related to various risks: dissemination of radioactive materials, exposure to ionizing radiations, criticality, fire and explosion, handling operations, loss of electric supplies or fluids, external aggression. Other events are those significant for the environment with a radiological component, or related to periodic controls and tests. The causes of these events are analysed. Specific events are presented which occurred on different sites (in the MELOX plant, in Areva sites in La Hague, Pierrelatte, in CEA sites in Cadarache and Saclay, in a fuel factory in Romans). Other topics are finally addressed: safety measures after the Fukushima accident, safety and radiation protection management systems of Areva and CEA, dismantling of nuclear installations

Proving test on the reliability for nuclear valves

International Nuclear Information System (INIS)

Kajiyama, Yasuo; Tashiro, Hisao; Uga, Takeo; Maeda, Shunichi.

1986-01-01

Since valves are the most common components, they could be the most frequent causes of troubles in nuclear power plants. This proving test, therefore, has an important meaning to examine and verify the reliability of various valves under simulating conditions of abnormal and transient operations of the nuclear power plant. The test was performed mainly for the various types and pressure ratings of valves which were used in the primary and secondary systems in BWR and PWR nuclear power plants and which had major operating or safety related functions in those nuclear power plants. The results of the proving test, confirmed for more than four years, showed relatively favourable performance of the tested valves. It is concluded that performances of valves including operability, seat sealing and structural integrity were proved under the thermal cycling, vibration and pipe reaction load conditions. Operating functions during and after accident such as loss of coolant accident were satisfactory. From these results, it was considered that the purpose of this proving test was satisfactorily fulfilled. Several data accumulated by the test would be useful to get better reliability if it was evaluated with the actually experienced data of valves in the nuclear power plants. (Nogami, K.)

Guidelines for DOE Long Term Civilian Research and Development. Volume III. Basic Energy Sciences, High Energy and Nuclear Physics

International Nuclear Information System (INIS)

1985-12-01

The Research Panel prepared two reports. This report reviews the Department of Energy's Basic Energy Sciences, High Energy Physics, and Nuclear Physics programs. The second report examines the Environment, Health and Safety programs in the Department. This summary addresses the general value and priority of basic research programs for the Department of Energy and the nation. In addition, it describes the key strategic issues and major recommendations for each program area

Nuclear cask testing films misleading and misused

Energy Technology Data Exchange (ETDEWEB)

Audin, L. (Audin (Lindsay), Ossining, NY (United States))

1991-10-01

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests.

Nuclear cask testing films misleading and misused

Energy Technology Data Exchange (ETDEWEB)

Audin, L. [Audin (Lindsay), Ossining, NY (United States)

1991-10-01

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ``proof`` to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests.

Nuclear cask testing films misleading and misused

International Nuclear Information System (INIS)

Audin, L.

1991-10-01

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ''proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests

Protection of Basic Nuclear Installations Against External Flooding - Guide No. 13

International Nuclear Information System (INIS)

2013-01-01

The French regulations require that the flooding hazard be taken into consideration in the demonstration of nuclear safety of basic nuclear installations (BNI). This guide details the recommendations concerning the external flooding hazard which is defined, for the purpose of this guide, as being a flood whose origin is external to the structures, areas or buildings of the BNI accommodating systems or components to be protected, whatever the cause(s) of that flooding (rainfall, river spates, storms, pipes failures, etc.). An external flood therefore means any flood originating outside the perimeter of the BNI and certain floods originating within the BNI perimeter. The terms 'flood' or 'flooding' as used henceforth designate external flooding. The purpose of this guide is to: - define the situations to consider when assessing the flood hazard for the site in question; - propose an acceptable method of quantifying them; - list recommendations for defining means of protection adapted to the specifics of the flooding hazard, implemented by the licensee according to the life cycle phases of the installation. The guide has taken climate change into account when the state of knowledge so allows. It is necessary to take into account - on the basis of current knowledge - the predictable climate changes for a period representative of the installations' foreseeable life times, and until the next safety review. The use of this guide necessitates prior identification - for the installation in question - of the functions required to demonstrate nuclear safety and which shall be preserved in the event of flooding. These functions are called 'safety functions' in this guide. This guide applies to all the basic nuclear installations defined by article L. L.593-2 of the Environment Code. With regard to radioactive waste disposal installations, this guide only applies to above-ground facilities. This guide can be used to assess the external flooding hazards and the associated

Optimizing Tuberculosis Testing for Basic Laboratories

Science.gov (United States)

Ramos, Eric; Schumacher, Samuel G.; Siedner, Mark; Herrera, Beatriz; Quino, Willi; Alvarado, Jessica; Montoya, Rosario; Grandjean, Louis; Martin, Laura; Sherman, Jonathan M.; Gilman, Robert H.; Evans, Carlton A.

2010-01-01

Optimal tuberculosis testing usually involves sputum centrifugation followed by broth culture. However, centrifuges are biohazardous and scarce in the resource-limited settings where most tuberculosis occurs. To optimize tuberculosis testing for these settings, centrifugation of 111 decontaminated sputum samples was compared with syringe-aspiration through polycarbonate membrane-filters that were then cultured in broth. To reduce the workload of repeated microscopic screening of broth cultures for tuberculosis growth, the colorimetric redox indicator 2,3-diphenyl-5-(2-thienyl) tetrazolium chloride was added to the broth, which enabled naked-eye detection of culture positivity. This combination of filtration and colorimetric growth-detection gave similar results to sputum centrifugation followed by culture microscopy regarding mean colony counts (43 versus 48; P = 0.6), contamination rates (0.9% versus 1.8%; P = 0.3), and sensitivity (94% versus 95%; P = 0.7), suggesting equivalency of the two methods. By obviating centrifugation and repeated microscopic screening of cultures, this approach may constitute a more appropriate technology for rapid and sensitive tuberculosis diagnosis in basic laboratories. PMID:20889887

Some Qualitative Requirements for Testing of Nuclear Emergency Response Robots

International Nuclear Information System (INIS)

Eom, Heungseop; Cho, Jai Wan; Choi, Youngsoo; Jeong, Kyungmin

2014-01-01

Korea Atomic Energy Research Institute (KAERI) is carrying out the project 'Development of Core Technology for Remote Response in Nuclear Emergency Situation', and as a part of the project, we are studying the reliability and performance requirements of nuclear emergency response robots. In this paper, we described some qualitative requirements for testing of nuclear emergency response robots which are different to general emergency response robots. We briefly introduced test requirements of general emergency response robots and described some qualitative aspects of test requirements for nuclear emergency response robots. When considering an immature field-robot technology and variety of nuclear emergency situations, it seems hard to establish quantitative test requirements of these robots at this time. However, based on studies of nuclear severe accidents and the experience of Fukushima NPP accident, we can expect some test requirements including quantitative ones for nuclear emergency response robots

Models test on dynamic structure-structure interaction of nuclear power plant buildings

International Nuclear Information System (INIS)

Kitada, Y.; Hirotani, T.

1999-01-01

A reactor building of an NPP (nuclear power plant) is generally constructed closely adjacent to a turbine building and other buildings such as the auxiliary building, and in increasing numbers of NPPs, multiple plants are being planned and constructed closely on a single site. In these situations, adjacent buildings are considered to influence each other through the soil during earthquakes and to exhibit dynamic behaviour different from that of separate buildings, because those buildings in NPP are generally heavy and massive. The dynamic interaction between buildings during earthquake through the soil is termed here as 'dynamic cross interaction (DCI)'. In order to comprehend DCI appropriately, forced vibration tests and earthquake observation are needed using closely constructed building models. Standing on this background, Nuclear Power Engineering Corporation (NUPEC) had planned the project to investigate the DCI effect in 1993 after the preceding SSI (soil-structure interaction) investigation project, 'model tests on embedment effect of reactor building'. The project consists of field and laboratory tests. The field test is being carried out using three different building construction conditions, e.g. a single reactor building to be used for the comparison purposes as for a reference, two same reactor buildings used to evaluate pure DCI effects, and two different buildings, reactor and turbine building models to evaluate DCI effects under the actual plant conditions. Forced vibration tests and earthquake observations are planned in the field test. The laboratory test is planned to evaluate basic characteristics of the DCI effects using simple soil model made of silicon rubber and structure models made of aluminum. In this test, forced vibration tests and shaking table tests are planned. The project was started in April 1994 and will be completed in March 2002. This paper describes an outline and the summary of the current status of this project. (orig.)

The needs of basic chemistry studies for nuclear waste management issues

International Nuclear Information System (INIS)

Guillaumont, R.

2004-01-01

There are several strategies to manage the radioactive matter which has taken the status of 'ultimate radwaste'. They are based on combinations of the three primary strategies: 'Wait for Decay', 'Concentrate and Confine' and 'Disperse and Dilute' the radio-toxic radionuclides and chemo-toxic elements. They are, or will be used for safe storage (interim and long term) or safe disposal of nuclear wastes. The chemical needs to apply these strategies are on materials for isolation, matrices for confinement and on the numerous aspects of the migration of the elements, both in the lithosphere and in the biosphere. According to the ultimate fate of long lived radionuclides which will be finally released into the environment, migration studies of elements are, or should be, the driving force of research in nuclear wastes management. The chemical needs for improving our present basic knowledge related to this field will be reviewed, with emphasis on some new topics and on the effects of concentration of the elements when they migrate. The necessity to open some 'dark boxes' will be outlined. The paper does not intend to give programs of researches but only tracks for future research. (authors)

Testing of nuclear air-cleaning systems

International Nuclear Information System (INIS)

Anon.

1975-01-01

A standard is presented which describes methods for field-testing nuclear power plant air cleaning systems. Included are specifications for visual inspection; duct and housing leak test; mounting frame pressure leak test; airflow capacity, distribution, and residence time tests; air-aerosol mixing uniformity test; in place leak test of HEPA filter banks; multiple sampling technique; in-place leak test of adsorber stage; laboratory testing of adsorbent; and duct heater performance test

Field test of wireless sensor network in the nuclear environment

International Nuclear Information System (INIS)

Li, L.; Wang, Q.; Bari, A.; Deng, C.; Chen, D.; Jiang, J.; Alexander, Q.; Sur, B.

2014-01-01

Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

Field test of wireless sensor network in the nuclear environment

Energy Technology Data Exchange (ETDEWEB)

Li, L., E-mail: lil@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Wang, Q.; Bari, A. [Univ. of Western Ontario, London, Ontario (Canada); Deng, C.; Chen, D. [Univ. of Electronic Science and Technology of China, Chengdu, Sichuan (China); Jiang, J. [Univ. of Western Ontario, London, Ontario (Canada); Alexander, Q.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2014-06-15

Wireless sensor networks (WSNs) are appealing options for the health monitoring of nuclear power plants due to their low cost and flexibility. Before they can be used in highly regulated nuclear environments, their reliability in the nuclear environment and compatibility with existing devices have to be assessed. In situ electromagnetic interference tests, wireless signal propagation tests, and nuclear radiation hardness tests conducted on candidate WSN systems at AECL Chalk River Labs are presented. The results are favourable to WSN in nuclear applications. (author)

Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

International Nuclear Information System (INIS)

Herman, Mike; Hoblit, Sam; Gustavo, Nobre; Palumbo, Annalia; Pigni, M.T.; Palmiotti, G.; Hiruta, H.; Salvatores

2013-01-01

neutron energy spectrum that are adopted in the assimilation (adjustment). In fact, after such an adjustment is performed, neutronic designers are then tied to this energy group structure and neutron energy spectrum when carrying out further calculations. In reality, this can be quite a limiting factor in view of the complex spectral issues that are involved in most reactor physics. This work combines novel, but proven, methodologies for overcoming these limitations. In fact, this is the first attempt to build up a link between the wealth of precise integral experiments and a basic theory of nuclear reactions. Essential ingredients of such a procedure, denominated here as assimilation, are covariances for model parameters and sensitivity matrices. The latter provide direct link between reaction theory and integral experiments. The result is a consistent data assimilation performed directly on the basic nuclear physics parameters that are being used in a variety of nuclear reaction mechanisms. The resulting improvement in their performance will consequently reduce related uncertainties when employed in reactor calculations. By using integral reactor physics experiments (meter scale), information is propagated back to the nuclear physics level (femtometers) covering a range of more than 13 orders of magnitude. The assimilation procedure should result in more accurate and more reliable evaluated data files of universal validity rather than tailored to a particular application. In fact, after data assimilation is carried out, the basic nuclear data file can be processed by a dedicated code into any energy group structure that the reactor physicist deems to be useful. On the other hand, integral experiments used in the assimilation should provide additional, possibly quite strict, constraints on the parameters entering nuclear reaction modeling, as well as the reaction models themselves. This report describes three years of combined research by Brookhaven National Lab (BNL

Basic principles

International Nuclear Information System (INIS)

Wilson, P.D.

1996-01-01

Some basic explanations are given of the principles underlying the nuclear fuel cycle, starting with the physics of atomic and nuclear structure and continuing with nuclear energy and reactors, fuel and waste management and finally a discussion of economics and the future. An important aspect of the fuel cycle concerns the possibility of ''closing the back end'' i.e. reprocessing the waste or unused fuel in order to re-use it in reactors of various kinds. The alternative, the ''oncethrough'' cycle, discards the discharged fuel completely. An interim measure involves the prolonged storage of highly radioactive waste fuel. (UK)

Expert systems - basic principles and possible applications in nuclear energy

International Nuclear Information System (INIS)

Cain, D.G.; Schmidt, F.

1987-01-01

One of the primary goals of the application of mathematical methods and computational techniques in reactor physics is the effective and accurate solution of the neutron diffusion equation under various conditions. To reach this goal still requires much skill, experience, knowledge and imagination as can be seen from various contributions at this and other conferences. Experts are necessary. Will expert systems replace them. We shall discuss this question by describing the basic principles of problem solving by expert systems as compared to problem solving by mathematical and computational methods. From this we shall identify areas of possible applications of the new techniques in nuclear energy and develop some thoughts on present limitations. As a result we conclude that expert systems will not be able to replace experts as long as the experts use the systems to improve their own expertise

Australia: Comprehensive Nuclear Test Ban Treaty. Model Treaty text

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

The scope of the proposed Treaty includes the following: Each State Party undertakes not to carry out any nuclear weapon test explosion, and to prohibit and prevent any such nuclear explosion at any place under its jurisdiction or control; each State Party undertakes, furthermore, to refrain from causing, encouraging, or in any way participating in the carrying out of any nuclear weapon tests explosion or any other nuclear explosion

Procedures and techniques for monitoring the radiation detection, signalization and alarm systems in the centralized ambience monitoring systems of the basic nuclear facilities of the CEN Saclay

International Nuclear Information System (INIS)

Andre, J.-J.; Drouet, J.; Leblanc, P.

1979-01-01

After referring to the regulations governing the 'systematic ambience monitoring' in the basic nuclear facilities, the main radiation detection, signalization and alarm devices existing at present in these facilities of the Saclay Nuclear Study Centre are described. The analysis of the operating defects of the measuring channels and detection possibilities leads to the anomalies being classified in two separate groups: the anomalies of the logical 'all or nothing' type of which all the possible origins are integrated into a so-called 'continuity' line and the evolutive anomalies of various origins corresponding to poor functioning extending possibly to a complete absence of signal. The techniques for testing the detection devices of the radiation monitoring board set up in the 'Departement de Rayonnements' at the Saclay Nuclear Study Centre are also described [fr

The Nuclear Non-Proliferation Treaty and the Comprehensive Nuclear-Test-Ban Treaty, the relationship

Energy Technology Data Exchange (ETDEWEB)

Graham, Thomas Jr. [7609 Glenbrook Rd., Bethesda, MD 20814 (United States)

2014-05-09

The Nuclear Non-Proliferation Treaty (NPT) is the most important international security arrangement that we have that is protecting the world community and this has been true for many years. But it did not happen by accident, it is a strategic bargain in which 184 states gave up the right forever to acquire the most powerful weapon ever created in exchange for a commitment from the five states allowed to keep nuclear weapons under the NPT (U.S., U.K., Russia, France and China), to share peaceful nuclear technology and to engage in disarmament negotiations aimed at the ultimate elimination of their nuclear stockpiles. The most important part of this is the comprehensive nuclear test ban (CTBT); the thinking by the 184 NPT non-nuclear weapon states was and is that they understand that the elimination of nuclear weapon stockpiles is a long way off, but at least the NPT nuclear weapon states could stop testing the weapons. The CTBT has been ratified by 161 states but by its terms it can only come into force if 44 nuclear potential states ratify; 36 have of the 44 have ratified it, the remaining eight include the United States and seven others, most of whom are in effect waiting for the United States. No state has tested a nuclear weapon-except for complete outlier North Korea-in 15 years. There appears to be no chance that the U.S. Senate will approve the CTBT for ratification in the foreseeable future, but the NPT may not survive without it. Perhaps it is time to consider an interim measure, for the UN Security Council to declare that any future nuclear weapon test any time, anywhere is a 'threat to peace and security', in effect a violation of international law, which in today's world it clearly would be.

The Basics of Hacking and Penetration Testing Ethical Hacking and Penetration Testing Made Easy

CERN Document Server

Engebretson, Patrick

2011-01-01

The Basics of Hacking and Penetration Testing serves as an introduction to the steps required to complete a penetration test or perform an ethical hack. You learn how to properly utilize and interpret the results of modern day hacking tools; which are required to complete a penetration test. Tool coverage will include, Backtrack Linux, Google, Whois, Nmap, Nessus, Metasploit, Netcat, Netbus, and more. A simple and clean explanation of how to utilize these tools will allow you  to gain a solid understanding of each of the four phases and prepare them to take on more in-depth texts and topi

A Short Test for the Assessment of Basic Knowledge in Psychology

Science.gov (United States)

Peter, Johannes; Leichner, Nikolas; Mayer, Anne-Kathrin; Krampen, Günter

2015-01-01

This paper reports the development of a fixed-choice test for the assessment of basic knowledge in psychology, for use with undergraduate as well as graduate students. Test content is selected based on a core concepts approach and includes a sample of concepts which are indexed most frequently in common introductory psychology textbooks. In a…

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

International Nuclear Information System (INIS)

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

1980-01-01

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

Analysis of changes in the federal funding trends to higher education for basic research in space, solar, and nuclear sciences compared to government and industry: 1967-1985

International Nuclear Information System (INIS)

Veasey, C. Jr.

1985-01-01

The problem addressed by this study is that the amount of federal funds allocated in higher education for conducting basic research in space, solar, and nuclear sciences appear to be declining relative to government and industry. To test this hypothesis, data were obtained from the National Science Foundation on the amounts of federal funds provided for research and development from fiscal years 1955 to 1985. The NSF data were organized into tables, presented, and analyzed to help determine what changes had occurred in the amounts of federal funds allocated to higher education, government, and industry for basic research in space, solar, and nuclear sciences for fiscal years 1967 to 1985. The study provided six recommendations to augment declining federal funds for basic research. (1) Expand participation in applied research, (2) Develop and expand consortia arrangements with other academic institutions of higher education. (3) Pursue other funding sources such as alumni, private foundations, industry, and state and local government. (4) Develop and expand joint research with national and industrial laboratories. (5) Expand participation in interdisciplinary and multidisciplinary research to develop technological solutions to local, regional, and national problems. (6) Develop and expand programs of reciprocal internships, and sabbaticals with industrial and national laboratories

Determination of the standards of the thermo-physiological tolerance for working in basic nuclear installation in TIVA protective clothing

International Nuclear Information System (INIS)

Casanova, P.; Daret, J.L.; Besnard, Y.; Clerc, N.; Savourey, G.; Launay, J.C.

2011-01-01

The purpose of this study was to determine the duration limited exposure (DLE) for working in a contaminated zone in a basic nuclear installation using the new ventilated TIVA protective clothing. Five subjects underwent a treadmill exercise (3.5 km/h, 3% of slope) of up to 2 h in a climatic chamber at 25, 35, and 45 deg. C. Cardiac frequency, rectal temperature and skin temperature were continuously recorded. The dehydration level was measured by the loss of weight during the exercise. At 25 deg. C, thermal and cardiovascular thresholds are not reached; the risk is dehydration if the exercise is prolonged. In contrast, the thresholds for Tre at 39 deg. C (97 ± 29 and 69 ± 28 min for 35 and 45 deg. C, respectively) and for the increase in Tre (+1.5 deg. C) are reached earlier (84 ± 38 min and 57 ± 21 min at 35 and 45 deg. C, respectively). This leads to a higher heat storage (42.2 ± 22.9 W/m 2 and 63.7 ± 29.4 W/m 2 , at 35 and 45 deg. C, respectively), which constitutes a higher risk of heat illnesses. The dehydration level is 2% of the weight for the tests at 35 and 45 deg. C. As a consequence, DLE for working in a contaminated zone in a basic nuclear installation in environmental conditions and using the new ventilated TIVA protective clothing, as encountered in our experiments, are proposed to avoid hyperthermic accidents. (authors)

Environmental contamination due to nuclear weapon tests and peaceful uses of nuclear explosions

International Nuclear Information System (INIS)

Petr, I.; Jandl, J.

1979-01-01

The effect of nuclear weapons tests and of the peaceful uses of nuclear explosions on the environment is described. The local and global fallout and the fallout distribution are analysed for the weapon tests. The radiation effects of external and internal irradiation on the population are discussed and the overall radiation risk is estimated. (author)

Reload Startup Physics Tests for Tianwan Nuclear Power station

International Nuclear Information System (INIS)

Yang Xiaoqiang; Li Wenshuang; Li Youyi; Yao Jinguo; Li Zaipeng Jiangsu

2010-01-01

This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)

Accuracy analysis of the CTBTO nuclear test detection scale and Improvement

Energy Technology Data Exchange (ETDEWEB)

Ryu, Young Kwang [Seoul National Univ., Seoul (Korea, Republic of)

2014-10-15

CTBTO (Comprehensive nuclear Test Ban Treaty Organization) is charge of nuclear test monitoring for nuclear non-proliferation. CTBTO has 170 seismic stations in operation in 76 countries in order to detect the artificial earthquake that was caused by an underground nuclear test. Korea use formula that is based on the equations that are used by the IMS (International Monitoring System) of CTBTO for analysis of explosive scale, and reflect the nature of the terrain, such as rock. But the expression for calculating the exact scale explosive is still un-established state. And generally CTBTO doesn't care about artificial explosive that is being received low-yield in accordance with the criteria of nuclear detection. But, at the time that North Korea conduct a nuclear test, it should not be overlooked that the scale of the earthquake detection criteria below. Because DPRK is trying to conceal their nuclear development capability, there are possibility of low-yield nuclear test or possibility of install a buffer to hide actual explosive scale. These radionuclide observations were consistent with a DPRK low-yield nuclear test on May 2010, even though no seismic signals from such a test have been detected. But there were a few times of low-yield (magnitude 1.39-1.93) occurred around DPRK nuclear test site at that time.

ACER Tests of Basic Skills: Aspects of Literacy, Aspects of Numercy. Teacher's Manual. Blue Series 6.

Science.gov (United States)

Lokan, Jan; And Others

Developed for the Basic Skills Testing Program (BSTP) in New South Wales, Australia, this teacher's manual describes the ACER (Australian Council for Educational Research) Tests of Basic Skills. The two tests in this series, Aspects of Literacy and Aspects of Numeracy, were administered statewide by government school classroom teachers in August,…

ACER Tests of Basic Skills: Aspects of Literacy, Aspects of Numeracy. Teacher's Manual. Green Series 6.

Science.gov (United States)

Lokan, Jan; And Others

Developed for the Basic Skills Testing Program (BSTP) in New South Wales, Australia, this teacher's manual describes the Green Series 6 of the ACER (Australian Council for Educational Research) Tests of Basic Skills. The two tests in this series, Aspects of Literacy and Aspects of Numeracy, were administered statewide by government school…

ACER Tests of Basic Skills: Aspects of Literacy, Aspects of Numeracy. Teacher's Manual. Blue Series 3.

Science.gov (United States)

Lokan, Jan; And Others

Developed for the Basic Skills Testing Program (BSTP) in New South Wales, Australia, this teacher's manual describes the Blue Series 3 of the ACER (Australian Council for Educational Research) Tests of Basic Skills. The two tests in the series, Aspects of Literacy and Aspects of Numeracy, were administered statewide by government school classroom…

ACER Tests of Basic Skills: Aspects of Literacy, Aspects of Numeracy. Teacher's Manual. Green Series 3.

Science.gov (United States)

Lokan, Jan; And Others

Developed for the Basic Skills Testing Program (BSTP) in New South Wales, Australia, this teacher's manual describes the Green Series 3 of the ACER (Australian Council for Educational Research) Tests of Basic Skills. The two tests in this series, Aspects of Literacy and Aspects of Numeracy, were administered statewide by government school…

Geologic surface effects of underground nuclear testing, Yucca Flat, Nevada Test Site, Nevada; TOPICAL

International Nuclear Information System (INIS)

Grasso, D.N.

2000-01-01

This report presents a new Geographic Information System composite map of the geologic surface effects caused by underground nuclear testing in the Yucca Flat Physiographic Area of the Nevada Test Site, Nye County, Nevada. The Nevada Test Site (NTS) was established in 1951 as a continental location for testing nuclear devices (Allen and others, 1997, p.3). Originally known as the ''Nevada Proving Ground'', the NTS hosted a total of 928 nuclear detonations, of which 828 were conducted underground (U.S. Department of Energy, 1994). Three principal testing areas of the NTS were used: (1) Yucca Flat, (2) Pahute Mesa, and (3) Rainier Mesa including Aqueduct Mesa. Underground detonations at Yucca Flat and Pahute Mesa were typically emplaced in vertical drill holes, while others were tunnel emplacements. Of the three testing areas, Yucca Flat was the most extensively used, hosting 658 underground tests (747 detonations) located at 719 individual sites (Allen and others, 1997, p.3-4). Figure 1 shows the location of Yucca Flat and other testing areas of the NTS. Figure 2 shows the locations of underground nuclear detonation sites at Yucca Flat. Table 1 lists the number of underground nuclear detonations conducted, the number of borehole sites utilized, and the number of detonations mapped for surface effects at Yucca Flat by NTS Operational Area

The struggle of the veterans of the French nuclear tests

International Nuclear Information System (INIS)

2005-01-01

The question debated in this article concerns the demand of compensation and recognition of the impact on their health of nuclear tests. The military personnel that worked during nuclear tests in French Polynesia and the Sahara sites, but also the inhabitants of the atolls of Moruroa and Fangataufa equally in French Polynesia. An observatory of the veterans health has been created in order to improve the medical management of military personnel and former military personnel. An association 'Moruroa e tatou' contains the Polynesian former workers of the Nuclear tests of the Pacific and the association A.V.E.N. contains the veterans of nuclear tests. numerous examples are detailed. The question is tackled too for the consequences on health of the British nuclear tests, in Australia, Christmas Islands, and New Zealand. (N.C.)

A fuzzy-based reliability approach to evaluate basic events of fault tree analysis for nuclear power plant probabilistic safety assessment

International Nuclear Information System (INIS)

Purba, Julwan Hendry

2014-01-01

Highlights: • We propose a fuzzy-based reliability approach to evaluate basic event reliabilities. • It implements the concepts of failure possibilities and fuzzy sets. • Experts evaluate basic event failure possibilities using qualitative words. • Triangular fuzzy numbers mathematically represent qualitative failure possibilities. • It is a very good alternative for conventional reliability approach. - Abstract: Fault tree analysis has been widely utilized as a tool for nuclear power plant probabilistic safety assessment. This analysis can be completed only if all basic events of the system fault tree have their quantitative failure rates or failure probabilities. However, it is difficult to obtain those failure data due to insufficient data, environment changing or new components. This study proposes a fuzzy-based reliability approach to evaluate basic events of system fault trees whose failure precise probability distributions of their lifetime to failures are not available. It applies the concept of failure possibilities to qualitatively evaluate basic events and the concept of fuzzy sets to quantitatively represent the corresponding failure possibilities. To demonstrate the feasibility and the effectiveness of the proposed approach, the actual basic event failure probabilities collected from the operational experiences of the David–Besse design of the Babcock and Wilcox reactor protection system fault tree are used to benchmark the failure probabilities generated by the proposed approach. The results confirm that the proposed fuzzy-based reliability approach arises as a suitable alternative for the conventional probabilistic reliability approach when basic events do not have the corresponding quantitative historical failure data for determining their reliability characteristics. Hence, it overcomes the limitation of the conventional fault tree analysis for nuclear power plant probabilistic safety assessment

Current developments in mechanized non-destructive testing in nuclear power plants; Aktuelle Entwicklungen bei mechanisierten, zerstoerungsfreien Pruefungen in Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

Zeilinger, R. [intelligeNDT System und Services GmbH und Co. KG, Erlangen (Germany)

2008-01-15

Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

Nuclear stress tests, the contribution of accidentology; Stress tests nucleaires, l'apport de l'accidentologie

Energy Technology Data Exchange (ETDEWEB)

Seillan, Hubert; Guerinot, J.

2011-09-15

After having recalled the basic principles and designs of nuclear safety as they were defined until the 1970's, the author explains the technical backgrounds of design reviews and propositions which could be made for the French nuclear power plants. His approach is based on accidentology, notably from lessons learned from the Three Mile Island, Chernobyl and Fukushima accidents. From there, he draws principles of nuclear safety. He proposes a critical examination of these principles through a comparison with accidents which occurred in oil, gas and chemical industries (in Mexico in 1984, in Bhopal in 1984, on the Piper Alpha offshore platform in 1988)

Test study on safety features of station blackout accident for nuclear main pump

International Nuclear Information System (INIS)

Liu Xiajie; Wang Dezhong; Zhang Jige; Liu Junsheng; Yang Zhe

2009-01-01

The theoretical and experimental studies of reactor coolant pump accidents encountered nation-wide and world-wide were described. To investigate the transient hydrodynamic performance of reactor coolant pump (RCP) during the period of rotational inertia in the station blackout accident, some theoretical and experimental studies were carried out, and the analysis of the test results was presented. The experiment parameters, conditions and test methods were introduced. The flow-rate, rotate speed and vibrations were analyzed emphatically. The quadruplicate polynomial curve equation was used to simulate the flow-rate,rotate speed along with time. The test results indicate that the flow-rate and rotator speed decrease rapidly at the very beginning of cut power and the test results accord with the regulation of safety standard. The vibrant displacement of bearing seat is intensified at the moment of lose power, but after a certain period rotor shaft libration changes. The test and analysis results help to understand the hydrodynamic performance of nuclear primary pump under lost of power accident, and provide the basic reference for safety evaluation. (authors)

Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit

Science.gov (United States)

Mason, Lee; Palac, Donald; Gibson, Marc; Houts, Michael; Warren, John; Werner, James; Poston, David; Qualls, Arthur Lou; Radel, Ross; Harlow, Scott

2012-01-01

A joint National Aeronautics and Space Administration (NASA) and Department of Energy (DOE) team is developing concepts and technologies for affordable nuclear Fission Power Systems (FPSs) to support future exploration missions. A key deliverable is the Technology Demonstration Unit (TDU). The TDU will assemble the major elements of a notional FPS with a non-nuclear reactor simulator (Rx Sim) and demonstrate system-level performance in thermal vacuum. The Rx Sim includes an electrical resistance heat source and a liquid metal heat transport loop that simulates the reactor thermal interface and expected dynamic response. A power conversion unit (PCU) generates electric power utilizing the liquid metal heat source and rejects waste heat to a heat rejection system (HRS). The HRS includes a pumped water heat removal loop coupled to radiator panels suspended in the thermal-vacuum facility. The basic test plan is to subject the system to realistic operating conditions and gather data to evaluate performance sensitivity, control stability, and response characteristics. Upon completion of the testing, the technology is expected to satisfy the requirements for Technology Readiness Level 6 (System Demonstration in an Operational and Relevant Environment) based on the use of high-fidelity hardware and prototypic software tested under realistic conditions and correlated with analytical predictions.

Nuclear Hybrid Energy System Model Stability Testing

Energy Technology Data Exchange (ETDEWEB)

Greenwood, Michael Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cetiner, Sacit M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Fugate, David W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-04-01

A Nuclear Hybrid Energy System (NHES) uses a nuclear reactor as the basic power generation unit, and the power generated is used by multiple customers as combinations of thermal power or electrical power. The definition and architecture of a particular NHES can be adapted based on the needs and opportunities of different localities and markets. For example, locations in need of potable water may be best served by coupling a desalination plant to the NHES. Similarly, a location near oil refineries may have a need for emission-free hydrogen production. Using the flexible, multi-domain capabilities of Modelica, Argonne National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory are investigating the dynamics (e.g., thermal hydraulics and electrical generation/consumption) and cost of a hybrid system. This paper examines the NHES work underway, emphasizing the control system developed for individual subsystems and the overall supervisory control system.

A Teaching Method on Basic Chemistry for Freshman (II) : Teaching Method with Pre-test and Post-test

OpenAIRE

立木, 次郎; 武井, 庚二

2004-01-01

This report deals with review of a teaching method on basic chemistry for freshman in this first semester. We tried to review this teaching method with pre-test and post-test by means of the official and private questionnaires. Several hints and thoughts on teaching skills are obtained from this analysis.

The needs of basic chemistry studies for nuclear waste management issues

Energy Technology Data Exchange (ETDEWEB)

Guillaumont, R

2004-07-01

There are several strategies to manage the radioactive matter which has taken the status of 'ultimate radwaste'. They are based on combinations of the three primary strategies: 'Wait for Decay', 'Concentrate and Confine' and 'Disperse and Dilute' the radio-toxic radionuclides and chemo-toxic elements. They are, or will be used for safe storage (interim and long term) or safe disposal of nuclear wastes. The chemical needs to apply these strategies are on materials for isolation, matrices for confinement and on the numerous aspects of the migration of the elements, both in the lithosphere and in the biosphere. According to the ultimate fate of long lived radionuclides which will be finally released into the environment, migration studies of elements are, or should be, the driving force of research in nuclear wastes management. The chemical needs for improving our present basic knowledge related to this field will be reviewed, with emphasis on some new topics and on the effects of concentration of the elements when they migrate. The necessity to open some 'dark boxes' will be outlined. The paper does not intend to give programs of researches but only tracks for future research. (authors)

The Comprehensive Nuclear Test-ban Treaty : an overview

International Nuclear Information System (INIS)

1997-01-01

The Comprehensive Nuclear Test-Ban Treaty ushers in the post-nuclear testing era. The Treaty is the result of many years of intensive international negotiation, and is an impressive document of some 48 pages plus 15 pages of annexes which, by April 1997, 143 nations including New Zealand had signed. New Zealand has consistently maintained a strong opposition to the testing of nuclear weapons and has had a long involvement in negotiations towards this Treaty. This is the first of a series of articles on the Treaty, its enforcement, and its implications for New Zealand, and provides an overview of the treaty by means of a quick tour through its main provisions. (author)

Industrial nuclear gauges

International Nuclear Information System (INIS)

Bennerstedt, T.

1986-01-01

A great number of industrial nuclear gauges are used in Sweden. The administrative routines for testing, approval and licensing are briefly described. Safety standards, including basic ICRP criteria, are summarized and a theoretical background to the various measuring techniques is given. Numerous practical examples are given. (author)

Tritium as an indicator of venues for nuclear tests.

Science.gov (United States)

Lyakhova, O N; Lukashenko, S N; Mulgin, S I; Zhdanov, S V

2013-10-01

Currently, due to the Treaty on the Non-proliferation of Nuclear Weapons there is a highly topical issue of an accurate verification of nuclear explosion venues. This paper proposes to consider new method for verification by using tritium as an indicator. Detailed studies of the tritium content in the air were carried in the locations of underground nuclear tests - "Balapan" and "Degelen" testing sites located in Semipalatinsk Test Site. The paper presents data on the levels and distribution of tritium in the air where tunnels and boreholes are located - explosion epicentres, wellheads and tunnel portals, as well as in estuarine areas of the venues for the underground nuclear explosions (UNE). Copyright © 2013 Elsevier Ltd. All rights reserved.

Radiological criteria for underground nuclear tests

International Nuclear Information System (INIS)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry

Radiological criteria for underground nuclear tests

Energy Technology Data Exchange (ETDEWEB)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry.

Fears for literacy and numeracy as new nurses fail basic tests.

Science.gov (United States)

Learner, Sue

2006-08-16

The Nursing and Midwifery Council (NMC) has voiced concern over nurses' poor levels of English and maths after a third of newly qualified nurses failed a basic test set by a hospital as part of anew selection process.

Basic processes in nuclear forensics and analytical plan

International Nuclear Information System (INIS)

Venugopal, V.

2016-01-01

Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

YK1 Basic professional training course on nuclear safety, Finland

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

2005-01-01

In the fall of 2002, Finnish organizations re-evaluated the manpower situation and established an organizing committee to develop and organize basic post-graduate professional training of new recruits and staff members; especially for the acute needs of the new NPP project, but also to provide in the long-term a new generation of nuclear experts to replace the present generation which will retire within the next ten years. The organizing committee included representatives of the following organizations: Radiation and Nuclear Safety Authority STUK, nuclear power utilities TVO and Fortum, the Technical Research Centre of Finland VTT, the Lappeenranta and Helsinki Universities of Technology, LUT and HUT, respectively, and the Ministry of Trade and Industry, KTM. The committee decided to promptly organize a national training course on nuclear safety based on a similar course developed by the IAEA: the course structure and syllabus are alike. Although part of the course material is based on the IAEA material, it has been adapted to the Finnish conditions, and a large part of the material is completely new. The Finnish application was developed in order to make visible different standpoints of all organizations. The location of the first six-week course YK1 from September 2003 to February 2004 rotated between different organizations. There were altogether 120 lecturers and rehearsal, demonstration or excursion leaders. Half of them came from the utilities TVO and Fortum, a quarter from the authority STUK, and the rest from VTT, universities and others. The 51 participants of the course came from these same organisations. The lectures were held in Finnish, and the slides in Finnish were distributed to the participants. However, it is useful and even mandatory to know the terms also in English, and therefore the extended abstracts of the lectures were written in English. The YK1 course material was laid on the website of LUT to look for in advance or in more detail with

YK1 Basic professional training course on nuclear safety, Finland

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

2005-01-01

In the fall of 2002, Finnish organizations re-evaluated the manpower situation and established an organizing committee to develop and organize basic post-graduate professional training of new recruits and staff members; especially for the acute needs of the new NPP project, but also to provide in the long-term a new generation of nuclear experts to replace the present generation which will retire within the next ten years. The organizing committee included representatives of the following organizations: Radiation and Nuclear Safety Authority STUK, nuclear power utilities TVO and Fortum, the Technical Research Centre of Finland VTT, the Lappeenranta and Helsinki Universities of Technology, LUT and HUT, respectively, and the Ministry of Trade and Industry, KTM. The committee decided to promptly organize a national training course on nuclear safety based on a similar course developed by the IAEA: the course structure and syllabus are alike. Although part of the course material is based on the IAEA material, it has been adapted to the Finnish conditions, and a large part of the material is completely new. The Finnish application was developed in order to make visible different standpoints of all organizations. The location of the first six-week course YK1 from September 2003 to February 2004 rotated between different organizations. There were altogether 120 lecturers and rehearsal, demonstration or excursion leaders. Half of them came from the utilities TVO and Fortum, a quarter from the authority STUK, and the rest from VTT, universities and others. The 51 participants of the course came from these same organisations. The lectures were held in Finnish, and the slides in Finnish were distributed to the participants. However, it is useful and even mandatory to know the terms also in English, and therefore the extended abstracts of the lectures were written in English. The YK1 course material was laid on the website of LUT to look for in advance or in more detail with

A compilation of nuclear weapons test detonation data for U.S. Pacific ocean tests.

Science.gov (United States)

Simon, S L; Robison, W L

1997-07-01

Prior to December 1993, the explosive yields of 44 of 66 nuclear tests conducted by the United States in the Marshall Islands were still classified. Following a request from the Government of the Republic of the Marshall Islands to the U.S. Department of Energy to release this information, the Secretary of Energy declassified and released to the public the explosive yields of the Pacific nuclear tests. This paper presents a synopsis of information on nuclear test detonations in the Marshall Islands and other locations in the mid-Pacific including dates, explosive yields, locations, weapon placement, and summary statistics.

The 20th nuclear explosion test of the Peoples' Republic of China (underground nuclear test)

International Nuclear Information System (INIS)

Anon.

1977-01-01

(1) The New China News Agency and the Radio Peking announced that China conducted the underground nuclear explosion test on 17 October, 1976. However, no exact data concerning the data, the place and the scale of this test was stated in above announcement. (2) However, relatively high radioactivity than that of normal level was detected in the rain and dry fallout samples collected from several prefectures. (author)

On-site tests on the nuclear power plants

International Nuclear Information System (INIS)

Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

1996-01-01

On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

Thermal lattice benchmarks for testing basic evaluated data files, developed with MCNP4B

International Nuclear Information System (INIS)

Maucec, M.; Glumac, B.

1996-01-01

The development of unit cell and full reactor core models of DIMPLE S01A and TRX-1 and TRX-2 benchmark experiments, using Monte Carlo computer code MCNP4B is presented. Nuclear data from ENDF/B-V and VI version of cross-section library were used in the calculations. In addition, a comparison to results obtained with the similar models and cross-section data from the EJ2-MCNPlib library (which is based upon the JEF-2.2 evaluation) developed in IRC Petten, Netherlands is presented. The results of the criticality calculation with ENDF/B-VI data library, and a comparison to results obtained using JEF-2.2 evaluation, confirm the MCNP4B full core model of a DIMPLE reactor as a good benchmark for testing basic evaluated data files. On the other hand, the criticality calculations results obtained using the TRX full core models show less agreement with experiment. It is obvious that without additional data about the TRX geometry, our TRX models are not suitable as Monte Carlo benchmarks. (author)

Nuclear Analyses of Indian LLCB Test Blanket System in ITER

Science.gov (United States)

Swami, H. L.; Shaw, A. K.; Danani, C.; Chaudhuri, Paritosh

2017-04-01

Heading towards the Nuclear Fusion Reactor Program, India is developing Lead Lithium Ceramic Breeder (LLCB) tritium breeding blanket for its future fusion Reactor. A mock-up of the LLCB blanket is proposed to be tested in ITER equatorial port no.2, to ensure the overall performance of blanket in reactor relevant nuclear fusion environment. Nuclear analyses play an important role in LLCB Test Blanket System design & development. It is required for tritium breeding estimation, thermal-hydraulic design, coolants process design, radioactive waste management, equipment maintenance & replacement strategies and nuclear safety. The nuclear behaviour of LLCB test blanket module in ITER is predicated in terms of nuclear responses such as tritium production, nuclear heating, neutron fluxes and radiation damages. Radiation shielding capability of LLCB TBS inside and outside bio-shield was also assessed to fulfill ITER shielding requirements. In order to supports the rad-waste and safety assessment, nuclear activation analyses were carried out and radioactivity data were generated for LLCB TBS components. Nuclear analyses of LLCB TBS are performed using ITER recommended nuclear analyses codes (i.e. MCNP, EASY), nuclear cross section data libraries (i.e. FENDL 2.1, EAF) and neutronic model (ITER C-lite v.l). The paper describes a comprehensive nuclear performance of LLCB TBS in ITER.

Nuclear Materials Management for the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Jesse C. Schreiber

2007-01-01

The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

Yesterday's, today's and tomorrow's nuclear tests of India and Pakistan

International Nuclear Information System (INIS)

Duval, M.; Le Guelte, G.

1998-01-01

This paper presents the historical aspects that led India and Pakistan to develop nuclear weapons and to perform nuclear weapon tests: weapons acquisition: today's military capacity, help from foreign countries; motivations: nuclear programs, geo-political aspects; results and potentialities; consequences for the non-proliferation systems and for the cut-off convention and test-ban treaties; and the geo-strategic consequences of todays's military nuclear capacity of India and Pakistan. (J.S.)

8432 - Order of 29 March 1989 publishing the Agreement of the Council of Ministers of 3 March 1989 on approval of the Basic Nuclear Emergency Plan

International Nuclear Information System (INIS)

1989-04-01

The Order approves and reproduces the Basic Nuclear Emergency Plan. The Plan contains the instructions to be complied with when nuclear emergency plans are established at Province level in accordance with the radiological criteria laid down by the Nuclear Safety Council, in the event an area is affected by an accident originating in a nuclear power plant [fr

Techniques to eliminate nuclear weapons testing infrastructure at former Semipalatinsk test site

International Nuclear Information System (INIS)

Erofeev, I.E.; Kovalev, V.V.

2003-01-01

It was at the former Semipalatinsk Test Site where for the first time in the world the nuclear weapons testing infrastructure elimination was put into practice. Fundamentally new procedures for blasting operations have been developed by specialists of the Kazakh State Research and Production Center of Blasting Operations (KSCBO), National Nuclear Center of the Republic of Kazakhstan (NNC) and Degelen Enterprise to enhance reliability and provide safety during elimination of various objects and performance of large-scale experiments. (author)

Maintaining nutritional adequacy during a prolonged food crisis. [Basic foods for post-nuclear attack use

Energy Technology Data Exchange (ETDEWEB)

Franz, K.B.; Kearny, C.H.

1979-08-01

This handbook is the first to assemble nutritional information and make recommendations on the efficient use of unprocessed grains, beans, and other elemental foods during the aftermath of a nuclear war. These basic foods would constitute the main resources to combat famine after a major nuclear attack. Such an attack would reduce and probably eliminate most commercial food processing for many months. To decision makers, this handbook should prove useful on basic aspects of nutrition in a long-term survival situation. These decision makers might range from the heads of families to government officials. Recommendations for nutrition given by organizations experienced in crisis feeding are reviewed and compared. Based on the best nutritional information available, emergency dietary recommendations are made for minimum and intermediate goals. The emergency dietary recommendations are applied to food for practical survival rations. Long-term survival rations for Americans are evaluated. These rations are (1) ten single-food rations; (2) four cereal-legume rations, ratio 4:1; (3) four cereal-legume rations, ratio 8:1; and (4) four cereal-legume-dry milk rations. The 22 different survival rations are detailed and summarized in 20 tables which list their nutritional adequacies and deficiences. Expedient procedures are given by which basic foods may be processed and cooked to provide a more healthful diet than most Americans believe possible. Special attention is given to the requirements of infants, children, and pregnant or lactating women. The eleven appendixes provide a wealth of specialized information. Among these appendixes is one that summarizes new and improved expedient methods for removing radioactive fallout and other contaminants from water. Another appendix is a comprehensive account of ways to sprout seeds to produce vitamins and improve palatability. (ERB)

Nuclear explosives testing readiness evaluation

Energy Technology Data Exchange (ETDEWEB)

Valk, T.C.

1993-09-01

This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

Development of testing system for the thermo-mechanical fatigue crack analysis of nuclear power plant pipes

International Nuclear Information System (INIS)

Lee, Ho Jin; Kim, Maan Won; Lee, Bong Sang

2003-12-01

Fatigue crack growth analysis plays an important role in the structural integrity assessment or the service life calculation of the nuclear power plant pipes. To obtain the material properties as a basic data to achieve an accurate crack growth analysis, a lot of tests and numerical crack growth simulations have been done for decades. The BS 7910 or the ASME Boiler and Pressure Vessel Code Section XI, generally used to evaluate crack growth behavior, were made under the based on simple stress states or at the evaluated isothermal temperature. It is well known that the ASME code could sometimes give so conservative results in some cases of which the cracked components are experiencing with cyclic thermal shock. In this report, we suggested a method for the life assessment of a crack embedded in nuclear power plant pipes under the thermal-mechanical fatigue loads. We here use the numerical method to get the temperature history for thermal- mechanical fatigue crack growth test. And then we can calculate the remaining life time of the pipe by using the fracture mechanics and the test results together. For this purpose, we constructed a thermal-mechanical fatigue crack growth testing system. We also gave a lot of review about recent researches in the experimental field of thermal-mechanical fatigue analysis

Report of 5th new nuclear fuel research meeting, Yayoi Research Group. Trend of advanced basic research in nuclear fuel technical development

International Nuclear Information System (INIS)

1994-03-01

Theme of this meeting is 'Trend of advanced basic research in nuclear fuel technical development', and it was attempted to balance both sides of the basic research and the development. At the meeting, lectures were given on the chemical form of FPs in oxide fuel pins, the absorption of hydrogen of fuel cladding tubes, the application of hydride fuel to thorium cycle, the thermal properties of fuel cladding tubes, the preparation of NpN and heat conductivity, the high temperature chemical reprocessing of nitride fuel, the research on the annihilation treatment of minor actinide in fast reactors, the separation of TRU by dry process and the annihilation using a metallic fuel FBR. In this report, the summaries of the lectures are collected, and also the program of the meeting and the list of attendants are shown. (K.I.)

Thermohydraulic tests in nuclear fuel model

International Nuclear Information System (INIS)

Ladeira, L.C.D.; Navarro, M.A.

1984-01-01

The main experimental works performed in the Thermohydraulics Laboratory of the NUCLEBRAS Nuclear Technology Development Center, in the field of thermofluodynamics are briefly described. These works include the performing of steady-state flow tests in single tube test sections, and the design and construction of a rod bundle test section, which will be also used for those kind of testes. Mention is made of the works to be performed in the near future, related to steady-state and transient flow tests. (Author) [pt

Basic statistics for nuclear electronics

International Nuclear Information System (INIS)

Stanchi, L.

1981-01-01

The paper reports many equations of general utility in the non-destructive measurement of nuclear materials. Its content is the synthesis of several lectures given in various courses of nuclear electronics and non-destructive measurements. It does not contain original derivations but provides in a convenient format formulae which may be useful to experimenters in their daily work. General equations on variances and standard deviations as well as the probability of single observations are represented. The most common frequency distributions of events (binomial, normal, poissonian and interval) are presented and practical formulae are given. Particular attention is devoted to deadtime effects (even although the cascade of deadtimes is not considered) and to the regularizing effect of scalers. Finally a short examination of ratemeters and the resolution problem in detection and amplification chains is provided

Out-pile Test of Double Cladding Fuel Rod Mockups for a Nuclear Fuel Irradiation Test

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jaemin; Park, Sungjae; Kang, Younghwan; Kim, Harkrho; Kim, Bonggoo; Kim, Youngki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-05-15

An instrumented capsule for a nuclear fuel irradiation test has been developed to measure fuel characteristics, such as a fuel temperature, internal pressure of a fuel rod, a fuel pellet elongation and a neutron flux during an irradiation test at HANARO. In the future, nuclear fuel irradiation tests under a high temperature condition are expected from users. To prepare for this request, we have continued developing the technology for a high temperature nuclear fuel irradiation test at HANARO. The purpose of this paper is to verify the possibility that the temperature of a nuclear fuel can be controlled at a high temperature during an irradiation test. Therefore we designed and fabricated double cladding fuel rod mockups. And we performed out-pile tests using these mockups. The purposes of a out-pile test is to analyze an effect of a gap size, which is between an outer cladding and an inner cladding, on the temperature and the effect of a mixture ratio of helium gas and neon gas on the temperature. This paper presents the design and fabrication of double cladding fuel rod mockups and the results of the out-pile test.

Contamination mechanisms of air basin with tritium in venues of underground nuclear explosions at the former Semipalatinsk test site

International Nuclear Information System (INIS)

Lyakhova, O.N.; Lukashenko, S.N.; Larionova, N.V.; Tur, Y.S.

2012-01-01

During the period of testing from 1945 to 1962 at the territory of Semipalatinsk test site (STS) within the Degelen Mountains in tunnels, 209 underground nuclear explosions were produced. Many of the tunnels have seasonal water seepage in the form of streams, through which tritium migrates from the underground nuclear explosion (UNE) venues towards the surface. The issue of tritium contamination occupies a special place in the radioactive contamination of the environment. In this paper we assess the level and distribution of tritium in the atmospheric air of ecosystems with water seepage at tunnels № 176 and № 177, located on “Degelen” site. There has been presented general nature of tritium distribution in the atmosphere relative to surface of a watercourse which has been contaminated with tritium. The basic mechanisms were studied for tritium distribution in the air of studied ecosystems, namely, the distribution of tritium in the systems: water–atmosphere, tunnel air–atmosphere, soil water–atmosphere, vegetation–atmosphere. An analytical calculation of tritium concentration in the atmosphere by the concentration of tritium in water has been performed. There has experimentally obtained the dependence for predictive assessment of tritium concentrations in air as a function of tritium concentration in one of the inlet sources such as water, tunnel air, soil water, vegetation, etc.. The paper also describes the general nature of tritium distribution in the air in the area “Degelen”. - Highlights: ► The basic mechanisms for tritium distribution in the air of nuclear testing sites were examined. ► We researched the distribution of tritium in the systems such as water–atmosphere, tunnel air–atmosphere, soil water–atmosphere and vegetation–atmosphere. ► An analytical calculation of tritium concentration in the atmosphere was performed. ► We experimentally obtained the dependence for predictive assessment of tritium concentrations in

Technology Development for Integrated Safety Test of Spent Nuclear Fuel Transportation and Storage System

International Nuclear Information System (INIS)

Seo, Kiseog; Seo, J. S.; Lee, J. C.

2012-05-01

A dedicated review on the U. S. NRC Regulation 10 CFR Part 72 and regulatory guide NUREG/1536 has been performed. The safety requirements for spent nuclear fuel dry storage cask are analyzed and summarized in structural, thermal, shielding, criticality, materials, tests and maintenance aspects. Also a guideline for preparing the safety analysis report is provided. The heat flow analysis was performed by varying the dimensions of the heat flow test facility. From the heat flow analysis for the test facility, as the test facility became test facility. From the heat flow analysis for the test facility, as the test facility became bigger; the thermal effect became smaller. Therefore, the dimensions of the heat flow test facility was designed with 5m Χ 5m Χ 6m(H). Analyses of heat transfer characteristics and mechanism for spent PWR fuel assemblies, option study for production of the effective thermal conductivity and option study for effective thermal conductivity test have been performed to obtain the basic data for production of the effective thermal conductivity. It became clear that the diffusion coefficient of chloride ion of concrete remarkably increases along with the temperature rise, and that there is a linear relation between the logarithm values of the diffusion coefficients and the reciprocal of the temperature. It is understood to be able to express the temperature dependency of the diffusion coefficient roughly by an Arrhenius equation as the velocity coefficient is provided as the diffusion coefficient. The specifications and characteristics of storage facilities under operation including dual purpose casks were investigated. Components subject to material degradation were examined. Based on literature survey, investigating a drop analysis incorporating with material degradation, the basic data to develop an analysis methodology was obtained

Analysis of North Korea's Nuclear Tests under Prospect Theory

Energy Technology Data Exchange (ETDEWEB)

Lee, Han Myung; Ryu, Jae Soo; Lee, Kwang Seok; Lee, Dong Hoon; Jun, Eunju; Kim, Mi Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

North Korea has chosen nuclear weapons as the means to protect its sovereignty. Despite international society's endeavors and sanctions to encourage North Korea to abandon its nuclear ambition, North Korea has repeatedly conducted nuclear testing. In this paper, the reason for North Korea's addiction to a nuclear arsenal is addressed within the framework of cognitive psychology. The prospect theory addresses an epistemological approach usually overlooked in rational choice theories. It provides useful implications why North Korea, being under a crisis situation has thrown out a stable choice but taken on a risky one such as nuclear testing. Under the viewpoint of prospect theory, nuclear tests by North Korea can be understood as follows: The first nuclear test in 2006 is seen as a trial to escape from loss areas such as financial sanctions and regime threats; the second test in 2009 was interpreted as a consequence of the strategy to recover losses by making a direct confrontation against the United States; and the third test in 2013 was understood as an attempt to strengthen internal solidarity after Kim Jong-eun inherited the dynasty, as well as to enhance bargaining power against the United States. Thus, it can be summarized that Pyongyang repeated its nuclear tests to escape from a negative domain and to settle into a positive one. In addition, in the future, North Korea may not be willing to readily give up its nuclear capabilities to ensure the survival of its own regime.

Nuclear non-proliferation: Revisiting the basics. Carnegie international non-proliferation conference 2002. Washington, D.C., 14 November 2002

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

The 1970 Treaty on the Non-Proliferation of Nuclear Weapons (NPT), with 188 States party, represents the cornerstone of the global nuclear non-proliferation and disarmament effort - and despite recent challenges, it has never been more relevant than it is today. But the international community has to move forward, it is essential that a number of the basic assumptions should be revisited, and a number of new approaches reconsidered. A key assumption at the core of the NPT was that the asymmetry between nuclear-weapon States and non-nuclear-weapon States would gradually disappear. The nuclear non-proliferation regime has overall been successful - but with some shortcomings. Efforts to end nuclear weapons development achieved an important milestone with the conclusion of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) in September 1996, but the pace of progress has been sluggish among the 44 countries whose ratification is required for the treaty to enter into force - and the rejection of the CTBT by the US Senate in 1999 was a distinct setback. Negotiation of a Fissile Material Cut-Off Treaty (FMCT) continues to languish in Geneva, more than seven years after agreement was reached on a mandate. The 2000 NPT Review Conference, building on the package of decisions and resolutions that led to the indefinite extension of the NPT in 1995, resulted in a number of encouraging commitments, not least the 'unequivocal undertaking' by the nuclear-weapon States to accomplish the total elimination of their nuclear arsenals. But a scant two years later, we have moved sharply away from those commitments, with a number of the '13 steps' toward nuclear disarmament - such as 'irreversibility,' 'START II, START III and the ABM Treaty,' further 'unilateral' reductions in nuclear arsenals, 'increased transparency,' 'further reduction of non-strategic nuclear weapons,' and 'regular reports' on the implementation of Article VI of the NPT - left without concrete follow-up actions and in

Radioactive fallout in the southern hemisphere from nuclear weapons tests

International Nuclear Information System (INIS)

Moroney, J.R.

1979-11-01

Fallout in the southern hemisphere, and its origins in the national programs of atmospheric nuclear weapons testing in both hemispheres, are reviewed. Of the 390 nuclear tests conducted in the atmosphere to date, 53 were carried out in the southern hemisphere and it is the second phase of these, between 1966 and 1974, that is seen to have been responsible for the main fallout of short-lived fission products in the southern hemisphere. In contrast to this, the programs of atmospheric nuclear testing in the northern hemisphere up to 1962 are shown to have been the main source of long-lived fission products in fallout in the southern hemisphere. The course followed by this contamination through the environment of the southern hemisphere is traced for the national programs of nuclear testing after 1962 taken separately (France, China) and for the earlier national programs taken together (U.S.S.R., U.S.A. and U.K.). The impact on populations in the southern hemisphere of fallout from atmospheric nuclear weapons tests to date is assessed

DPRK's 4"t"h Nuclear Test and its Tritium Production

International Nuclear Information System (INIS)

Kim, Min Soo; Lee, Sang Joon; Chang, Sun Young

2016-01-01

On January 6, 2016 at 10:30am, the artificial earthquake in the DPRK was detected by multiple international seismic organizations. After 2 hours, the DPRK announced on state TV that 'The first H-bomb test was successfully conducted in the DPRK at 10:00 am on Wednesday, Juche 105(2016), pursuant to the strategic determination of the ruling communist party.' There has been a doubt about the real nature of the DPRK's 4th nuclear test, since 2 months have been passed after its nuclear test. To analyze the nature of the DPRK's nuclear test, it is necessary to check possible options for production of essential materials. The pathways to produce nuclear fusion material (tritium) and to have a relatively high possibility for the DPRK are described in this article. Tritium is key material for H-bomb. And there are two options for the DPRK which are 1) production and 2) illicit trafficking. And this study is focused on production possibility of DPRK. Determination of the nature of DPRK's nuclear test is very hard issue

Radioactive fallout in the southern hemisphere from nuclear weapons tests

International Nuclear Information System (INIS)

Moroney, J.R.

1979-01-01

Fallout in the southern hemisphere, and its origins in the national programs of atmospheric nuclear weapons testing in both hemispheres, are reviewed. Of the 390 nuclear tests conducted in the atmosphere to date, 53 were carried out in the southern hemisphere and it is the second phase of these, between 1966 and 1974, that is seen to have been responsible for the main fallout of short-lived fission products in the southern hemisphere. In contrast to this, the programs of atmospheric nuclear testing in the northern hemisphere up to 1962 are shown to have been the main source of long-lived fission products in fallout in the southern hemisphere. The course followed by this contamination through the environment of the southern hemisphere is traced for the national programs of nuclear testing after 1962 taken separately (France, China) and for the earlier national programs taken together (U.S.S.R., U.S.A. and U.K.). The impact on populations in the southern hemisphere of fallout from atmospheric nuclear weapons tests to date is assessed. (author)

MO-AB-206-00: Nuclear Medicine Physics and Testing

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

This education session will cover the physics and operation principles of gamma cameras and PET scanners. The first talk will focus on PET imaging. An overview of the principles of PET imaging will be provided, including positron decay physics, and the transition from 2D to 3D imaging. More recent advances in hardware and software will be discussed, such as time-of-flight imaging, and improvements in reconstruction algorithms that provide for options such as depth-of-interaction corrections. Quantitative applications of PET will be discussed, as well as the requirements for doing accurate quantitation. Relevant performance tests will also be described. Learning Objectives: Be able to describe basic physics principles of PET and operation of PET scanners. Learn about recent advances in PET scanner hardware technology. Be able to describe advances in reconstruction techniques and improvements Be able to list relevant performance tests. The second talk will focus on gamma cameras. The Nuclear Medicine subcommittee has charged a task group (TG177) to develop a report on the current state of physics testing of gamma cameras, SPECT, and SPECT/CT systems. The report makes recommendations for performance tests to be done for routine quality assurance, annual physics testing, and acceptance tests, and identifies those needed satisfy the ACR accreditation program and The Joint Commission imaging standards. The report is also intended to be used as a manual with detailed instructions on how to perform tests under widely varying conditions. Learning Objectives: At the end of the presentation members of the audience will: Be familiar with the tests recommended for routine quality assurance, annual physics testing, and acceptance tests of gamma cameras for planar imaging. Be familiar with the tests recommended for routine quality assurance, annual physics testing, and acceptance tests of SPECT systems. Be familiar with the tests of a SPECT/CT system that include the CT images

MO-AB-206-00: Nuclear Medicine Physics and Testing

International Nuclear Information System (INIS)

2016-01-01

This education session will cover the physics and operation principles of gamma cameras and PET scanners. The first talk will focus on PET imaging. An overview of the principles of PET imaging will be provided, including positron decay physics, and the transition from 2D to 3D imaging. More recent advances in hardware and software will be discussed, such as time-of-flight imaging, and improvements in reconstruction algorithms that provide for options such as depth-of-interaction corrections. Quantitative applications of PET will be discussed, as well as the requirements for doing accurate quantitation. Relevant performance tests will also be described. Learning Objectives: Be able to describe basic physics principles of PET and operation of PET scanners. Learn about recent advances in PET scanner hardware technology. Be able to describe advances in reconstruction techniques and improvements Be able to list relevant performance tests. The second talk will focus on gamma cameras. The Nuclear Medicine subcommittee has charged a task group (TG177) to develop a report on the current state of physics testing of gamma cameras, SPECT, and SPECT/CT systems. The report makes recommendations for performance tests to be done for routine quality assurance, annual physics testing, and acceptance tests, and identifies those needed satisfy the ACR accreditation program and The Joint Commission imaging standards. The report is also intended to be used as a manual with detailed instructions on how to perform tests under widely varying conditions. Learning Objectives: At the end of the presentation members of the audience will: Be familiar with the tests recommended for routine quality assurance, annual physics testing, and acceptance tests of gamma cameras for planar imaging. Be familiar with the tests recommended for routine quality assurance, annual physics testing, and acceptance tests of SPECT systems. Be familiar with the tests of a SPECT/CT system that include the CT images

Nuclear test at Semipalatinsk test site and their environmental impacts

International Nuclear Information System (INIS)

Logachev, V.A.

2000-01-01

This paper present classification of nuclear tests conducted at the Semipalatinsk test site by tier radiation hazards. The Institute of Biophysics of the Russian Ministry of Health established a data base the archival data on radiation situation parameters and compiled an album of radioactive plum footprints. The paper states that external and internal exposure doses received by population lived in the test vicinity can sufficiently reliably assesses using archival data. (author)

Joint experiment on verification of the treaty on the limitation of underground nuclear tests and its value in nuclear disarmament problem

International Nuclear Information System (INIS)

Mikhailov, V.N.

1998-01-01

This conference commemorates the 10th anniversary of the Joint Verification Experiment. The experiment was performed in order to specify methods controlling yield of underground explosions in the USA and the USSR. Basic of the the experiment were coordinated and formulated in the Agreement signed by Heads of departments of foreign policies in Moscow on 31 May 1988. The tasks can be briefly revealed the following way: - each of the parties can measure (on mutual basis) the explosion yield in the course of the experiment performed on the test site of the other party using tele seismic and hydrodynamic methods; - each party also makes tele seismic measurement of both explosions of the experiment with the help of its national net of seismic stations; - each party makes hydrodynamic measurements of explosion yield in the course of the experiment in a special additional borehole; - each party performs tele-seismic measurements of both explosions' yield at its five seismic stations with which the parties exchanged data on the explosions made earlier. In the course of the experiment the parties exchanged the data obtained in the same volume. The analysis showed: 1. The experiment conformed to all the requirements of the Agreement in spite of all the complexity of the procedures and differences in conditions of the experiment performance. 2. The experiment became an example of an unprecedented level of cooperation between two countries in one of the most significant for national security fields of defense activity. 3. The experiment gave the basis for concrete coordination of underground test yield control measures. It also considerable advanced the elaboration of protocols to treaties of 1974 and 1976. 4. In the course of the experiment there appeared an opportunity to compare scientific-technical level of hydrodynamic and seismic measurements and safety provision for nuclear tests of both countries. Cooperative development of anti intrusive devices for hydrodynamic method

Implementation of a basic principle simulator

International Nuclear Information System (INIS)

De Greef, J.F.

1982-01-01

During the last twenty years, the Belgian Nuclear Energy Centre (SCK-CEN) gained a lot of experience in mathematical modelling and simulation of nuclear reactor power plant operation. The framework, in which these activities took place, was mainly concerned with security analysis of these devices and with training operation personnel of these plants. In the last years a fourth generation hybrid computer including an AD/FIVE analog computer of Applied Dynamics Inc. (ADI) and a PDP-11/34 digital computer of Digital Equipment Corporation (DEC) were installed. Furthermore, a home made operator's desk simulating the elements of the control room of a nuclear power plant completes the computer system for real-time training purposes. The described equipment is typically that of a Basic Principle Simulator, a device that quickly and effectively imparts the basic concepts of a nuclear power plant operation

Semipalatinsk nuclear test site: History of building and function

International Nuclear Information System (INIS)

Sergazina, G.M.; Balmukhanov, S.B.

1999-01-01

A vast materials on history of Semipalatinsk nuclear test site creation and it building and function are presented. Authors with big reliability report one page of Kazakhstan's history. In steppe on naked place thousands of soldiers and officers, construct and military specialists have built the nuclear site on which during 40 years were conducting nuclear tests . Prolonged chronic radiation on population living near by site results to tragedy which is confessed by General Assembly of United Nations. In the book aspects of test site conversion and rehabilitation of injured population are considered. The book consists of introduction, three chapters and conclusion. The book is intended to wide circle of readers. (author)

Environmental assessment report: Nuclear Test Technology Complex

International Nuclear Information System (INIS)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report

Recent irradiation tests for future nuclear system at HANARO

Energy Technology Data Exchange (ETDEWEB)

Cho, Man Soon; Choo, Kee Nam; Yang, Seong Woo; Park, Sang Jun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-05-15

The capsule at HANARO is a device that evaluates the irradiation effects of nuclear materials and fuels, which can reproduce the environment of nuclear power plants and accelerate to reach to the end of life condition. As the integrity assessment and the extension of lifetime of nuclear power plants are recently considered as important issues in Korea, the requirements for irradiation test are gradually being increased. The capacity and capability irradiation tests at HANARO are becoming important because Korea strives to develop SFR (Sodium-cooled Fast Reactor) and VHTR (Very High Temperature Reactor) among the future nuclear system and to export the research reactors and to develop the fusion reactor technology.

Nuclear test-experimental science annual report, Fiscal year 1990

International Nuclear Information System (INIS)

Struble, G.L.; Middleton, C.; Anderson, S.E.; Cherniak, J.; Donohue, M.L.; Francke, A.; Hedman, I.; Kirvel, R.D.

1991-01-01

Fiscal year 1990 was another year of outstanding accomplishments for the Nuclear Test-Experimental Science (NTES) Program at Lawrence Livermore National Laboratory (LLNL). We continued to make progress to enhance the experimental science in the Weapons Program and to improve the operational efficiency and productivity of the Nuclear Test Program

Basic safety principles of KLT-40C reactor plants

International Nuclear Information System (INIS)

Beliaev, V.; Polunichev, V.

2000-01-01

The KLT-40 NSSS has been developed for a floating power block of a nuclear heat and power station on the basis of ice-breaker-type NSSS (Nuclear Steam Supply System) with application of shipbuilding technologies. Basic reactor plant components are pressurised water reactor, once-through coil-type steam generator, primary coolant pump, emergency protection rod drive mechanisms of compensate group-electromechanical type. Basic RP components are incorporated in a compact steam generating block which is arranged within metal-water shielding tank's caissons. Domestic regulatory documents on safety were used for the NSSS design. IAEA recommendations were also taken into account. Implementation of basic safety principles adopted presently for nuclear power allowed application of the KLT-40C plant for a floating power unit of a nuclear co-generation station. (author)

Guarantying and testing the nuclear safeguards

International Nuclear Information System (INIS)

Turcu, Ilie

2002-01-01

Apparently, the nuclear power will ensure an important share of the world energy demand at least for the next decades because there is no viable alternative in the fan of energy sources neither one complying with the environment preservation requirements. The nuclear energy future depends not only on technical and economical aspects but also on preventing any danger of nuclear safeguards nature. The main international legal instrument which provides concrete commitments for nations in this field is the Nuclear Safeguard Convention. It provides guarantees and testings of the nuclear safeguards over the entire service life of the nuclear power plants. In the two general conferences (of 1999 and 2002) the status and measures adopted in the field of nuclear safeguards by the states adhering to the convention were discussed and reviewed, as well as the issues of financial resources, licensing and the adequate measures in emergency cases. The nuclear safeguards is a major issue among the criteria of integration in UE. Essential for maintaining and endorsing the provisions of nuclear safeguards in Romania are specific research and development activities aiming at integrating the equipment and structures, solving the operation problems of nuclear facilities, studying the behavior of installations in transient regimes, investigating the reliability and probabilistic assessing of nuclear safeguards, examining the phenomenology and simulating severe accidents or human factor behavior. Of major importance appears to be the international cooperation aiming that a permanent exchange of information and experience, dissemination of the best results, solutions and practices. The paper presents the status and trends at the world level, as well as in Romania, underlining the main issues of the strategy in this field and stressing the financial and human resources implied the implementing the nuclear safeguards provisions

Traditional nuclear physics as a test of nuclear exotics

International Nuclear Information System (INIS)

Sapershtein, E.E.; Starodubskii, V.E.

1989-01-01

The review considers the testing of some exotic hypotheses about the properties of the nucleon in a nuclear medium in phenomena of traditional nuclear physics. The hypothesis of nucleon swelling proposed to explain the EMC effects is considered in detail. The consequences of this hypothesis for the charge densities and cross sections for scattering of fast electrons and protons by nuclei are analyzed. Also considered are the Nolen--Schiffer anomaly, the Coulomb sum rule for inelastic electron scattering, y scaling, and some other nuclear processes. It is shown that one can estimate the possible scale of nuclear exotics by analyzing many of these phenomena. Thus, examination of high-precision data on the elastic scattering of electrons with energy 500--700 MeV using density distributions calculated on the basis of the self-consistent theory of finite Fermi systems yields a restriction on the amount of nucleon swelling: α=δr N /r N approx-lt 10%. A similar analysis for protons with energy 0.8--1.0 GeV using Glauber theory gives α approx-lt 6%. An even more stringent restriction, α approx-lt 3%, follows from data on y scaling in 56 Fe

Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-11-15

This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

Basic research projects

International Nuclear Information System (INIS)

1979-04-01

The research programs under the cognizance of the Office of Energy Research (OER) are directed toward discovery of natural laws and new knowledge, and to improved understanding of the physical and biological sciences as related to the development, use, and control of energy. The ultimate goal is to develop a scientific underlay for the overall DOE effort and the fundamental principles of natural phenomena so that these phenomena may be understood, and new principles, formulated. The DOE-OER outlay activities include three major programs: High Energy Physics, Nuclear Physics, and Basic Energy Sciences. Taken together, these programs represent some 30 percent of the Nation's Federal support of basic research in the energy sciences. The research activities of OER involve more than 6,000 scientists and engineers working in some 17 major Federal Research Centers and at more than 135 different universities and industrial firms throughout the United States. Contract holders in the areas of high-energy physics, nuclear physics, materials sciences, nuclear science, chemical sciences, engineering, mathematics geosciences, advanced energy projects, and biological energy research are listed. Funding trends for recent years are outlined

Testing lifting systems in nuclear facilities

International Nuclear Information System (INIS)

Kling, H.; Laug, R.

1984-01-01

Lifting systems in nuclear facilities must be inspected at regular intervals after having undergone their first acceptance test. These inspections are frequently carried out by service firms which not only employ the skilled personnel required for such jobs but also make available the necessary test equipment. The inspections in particular include a number of sophisticated load tests for which test load systems have been developed to allow lifting systems to be tested so that reactor specific boundary conditions are taken into account. In view of the large number of facilities to be inspected, the test load system is a modular system. (orig.) [de

International Symposium of Scientists for Nuclear test Stopping

International Nuclear Information System (INIS)

Anon.

1986-01-01

Problems discussed at International Symposium of Scientists for Nuclear Test Stopping in July 1986 in Moscow were considered. Scientists discussed complex of possible measures directed at strengthening of peace supporting mechanism, spoke in support of prohibition of all nuclear weapon tests. Necessity of measures preventing the weapon delivery to space, construction of the regime of using cosmic equipment exclusively for peace was noted. Attention was paid to the problem of control for test stopping (by means of sattelites and seismic methods), cooperation establishment between the USSR Academy of Sciences and the Council for the protection of the USA Natural Resources

Safety at basic nuclear facilities other than nuclear power plants. Lessons learned from significant events reported in 2011 and 2012

International Nuclear Information System (INIS)

2014-01-01

The third report on the safety of basic nuclear installations in France other than power reactors presents an IRSN's analysis of significant events reported to the Nuclear Safety Authority in the years 2011 and 2012. It covers plants, laboratories, research reactors and facilities for the treatment, storage or disposal of waste. This report aims to contribute to a better understanding by stakeholders and more widely by the public of the safety and radiation protection issues associated with the operation of nuclear facilities, the progress made in terms of safety as well as the identified deficiencies. The main trend shows, once again, the significant role of organizational and human factors in the significant events that occurred in 2011 and 2012, of which the vast majority are without noteworthy consequences. Aging mechanisms are another major cause of equipment failure and require special attention. The report also provides IRSN's analysis of specific events that are particularly instructive for facility safety and a synthesis of assessments performed by IRSN on topics that are important for safety and radiation protection. IRSN also includes an overview of its analysis of measures proposed by licensees for increasing the safety of their facilities after the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan, which consist of providing a 'hardened safety core' to confront extreme situations (earthquake, flooding, etc.) that are unlikely but plausible and can bring about levels of hazards higher than those taken into account in the design of the facilities

Nuclear-physical methods in macro- and microanalytical investigations of contamination with radionuclides at Semipalatinsk Nuclear Test Site

International Nuclear Information System (INIS)

Solodukhin, V.P.

2005-01-01

A complex of nuclear-physical methods developed in the Institute of Nuclear Physics of Kazakhstan National Nuclear Center for the investigations of the rate, character and peculiarities of contamination with radionuclides of the Semipalatinsk Nuclear Test Site (SNTS) is presented. The developed method combines both macroinvestigations (radionuclide analysis, NAA, XRFA, ESR- and NGR-spectroscopy) and microinvestigations (MS, micro-PIXE, electron microscopy). The results of the investigations at the main SNTS test sites 'Opytnoye pole' and 'Degelen' are presented. (author)

Lightning vulnerability of nuclear explosive test systems at the Nevada Test Site

International Nuclear Information System (INIS)

Hasbrouck, R.T.

1985-01-01

A task force chartered to evaluate the effects of lightning on nuclear explosives at the Nevada Test Site has made several recommendations intended to provide lightning-invulnerable test device systems. When these recommendations have been implemented, the systems will be tested using full-threat-level simulated lightning

Measurement implications for effective testing in nuclear training

International Nuclear Information System (INIS)

Zaret, R.; Pawlowski, V.

1983-01-01

The primary thrust of this paper is to present an overview of the measurement concepts of reliability and validity. Techniques and issues are presented which will allow Nuclear Training Personnel to have greater confidence in the accuracy of scores obtained from in-house developed tests. While it is realized that the conditions under which tests are developed in Nuclear Training environments are less than ideal, the concepts and techniques addressed can be applied under any conditions

Microprocessors applications in the nuclear industry

International Nuclear Information System (INIS)

Ethridge, C.D.

1980-01-01

Microprocessors in the nuclear industry, particularly at the Los Alamos Scientific Laboratory, have been and are being utilized in a wide variety of applications ranging from data acquisition and control for basic physics research to monitoring special nuclear material in long-term storage. Microprocessor systems have been developed to support weapons diagnostics measurements during underground weapons testing at the Nevada Test Site. Multiple single-component microcomputers are now controlling the measurement and recording of nuclear reactor operating power levels. The CMOS microprocessor data-acquisition instrumentation has operated on balloon flights to monitor power plant emissions. Target chamber mirror-positioning equipment for laser fusion facilities employs microprocessors

On the population dose around the Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Hill, P.; Dederichs, H.; Ostapczuk, P.; Hille, R.; Artemev, O.; Ptitskaya, L.; Akhmetov, M.; Pivovarov, S.

2002-01-01

Since 1949 the Semipalatinsk Nuclear Test Site (NTS) was extensively used by the former Soviet government as a testing range for atomic weapons. Atmospheric and underground tests were finally stopped in 1962 and 1989, respectively. The Ministry of the Russian Federation of Atomic Energy officially counts a total of 456 tests, including 116 atmospheric tests. The total yield of the nuclear explosions carried out was 6.3 Megatons equivalent with 6.7 PetaBq of 1 37C s and 3.7 PetaBq of 9 0S r being released into the athmosphere. Some of the athmospheric radioactive tests shielded plumes, which extended far beyond the outer borders of the NTS. Already the first Soviet atomic bomb test on August 29, 1949 due to unfavourable meteorological conditions affected the villages of Dolon and Moistik. Since 1995 joint investigations performed by the Research Centre Julich in cooperation with the Kazakh National Nuclear Centre in the region of the former nuclear test site near Semipalatinsk besides environmental measurents also involve the assessment of the current dose of the population at and around the test site in addition to the important retrospective determination of the dose of persons affected by the atmospheric tests

Layout of the objects of underground nuclear tests at the Balapan test field of the former Semipalatinsk test site

International Nuclear Information System (INIS)

Konovalov, V.E.; Gryaznov, O.V.

2000-01-01

Integrated research of practical and scientific interest is conducted at the Balapan test field of the Semipalatinsk test site. The lack of the reliable locations for features associated with nuclear testing causes considerable difficulties while carrying out the research. To fill this gap the authors present data available at the Institute of Geophysical Research of the National Nuclear Center of the Republic of Kazakhstan. (author)

Physics with radioactive nuclear beams

International Nuclear Information System (INIS)

Boyd, R.N.; Tanihata, I.

1992-01-01

Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides. One goal, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell modelclose quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. 25 refs., 7 figs

Physics with radioactive nuclear beams

International Nuclear Information System (INIS)

Boyd, R.N.

1995-01-01

Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell model close quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. (author). 25 refs., 7 figs

An Evaluation of North Korea’s Nuclear Test by Belbasi Nuclear Tests Monitoring Center-KOERI

Science.gov (United States)

Necmioglu, O.; Meral Ozel, N.; Semin, K.

2009-12-01

Bogazici University and Kandilli Observatory and Earthquake Research Institute (KOERI) is acting as the Turkish National Data Center (NDC) and responsible for the operation of the International Monitoring System (IMS) Primary Seismic Station (PS-43) under Belbasi Nuclear Tests Monitoring Center for the verification of compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT) since February 2000. The NDC is responsible for operating two arrays which are part of the IMS, as well as for transmitting data from these stations to the International Data Centre (IDC) in Vienna. The Belbasi array was established in 1951, as a four-element (Benioff 1051) seismic array as part of the United States Atomic Energy Detection System (USAEDS). Turkish General Staff (TGS) and U.S. Air Force Technical Application Center (AFTAC) under the Defense and Economic Cooperation Agreement (DECA) jointly operated this short period array. The station was upgraded and several seismometers were added to array during 1951 and 1994 and the station code was changed from BSRS (Belbasi Seismic Research Station) to BRTR-PS43 later on. PS-43 is composed of two sub-arrays (Ankara and Keskin): the medium-period array with a ~40 km radius located in Ankara and the short-period array with a ~3 km radius located in Keskin. Each array has a broadband element located at the middle of the circular geometry. Short period instruments are installed at depth 30 meters from the surface while medium and broadband instruments are installed at depth 60 meters from surface. On 25 May 2009, The Democratic People’s Republic of Korea (DPRK) claimed that it had conducted a nuclear test. Corresponding seismic event was recorded by IMS and IDC released first automatic estimation of time (00:54:43 GMT), location (41.2896°N and 129.0480°E) and the magnitude (4.52 mb) of the event in less than two hours time (USGS: 00:54:43 GMT; 41.306°N, 129.029°E; 4.7 mb) During our preliminary analysis of the 25th May 2009 DPRK

SCOPE-RADTEST: Radioactivity from nuclear test explosions

International Nuclear Information System (INIS)

Shapiro, C.S.; Tsaturov, Y.

1993-10-01

The SCOPE-RADTEST program consists of an international collaborative study involving Russia, the USA, China, and Kazakhstan. It will focus on the releases of radioactivity that resulted from nuclear test explosions that have taken place at various test sites around the world for peaceful and military purposes. RADTEST will focus on these principal tasks: (1) To inventory data on measurements of radionuclide deposition densities, and identify gaps in these data. (2) To compare old and develop new models of radioactive transport to better understand the deposition densities of radionuclides both on and near the nuclear test sites, including areas downwind where potentially significant episodes of fallout have occurred (such as the Altaj Region of Russia). (3) To study the migration of the radionuclides through the biosphere, including all pathways to humans. This will include the study of the effects on other biota that have impacts on humans. The main focus will be to characterize the nature and magnitude of the dose to humans. This will include dose reconstructions from past events, and also an increased capability for dose prediction from possible future accidental or deliberate explosions. (4)To analyze the data on the effects of these doses (including low doses) on human health. The test sites to be studied would include the Nevada Test Site (USA), South Pacific Islands (USA), Novaja Zemla (Russia), Semipalatinsk (Kazakhstan) and Luc Bu Pu (Lop Nor) (China). Tests at these sites include most of the total of nuclear explosions that have been conducted. Other sites, (including the sites of the U.K. and France), as appropriate, may also be included where tests were conducted for peaceful or military purposes

The need to qualify Non Destructive Tests (NDT) has been recognized for many years in the European countries engaged in nuclear power generation

International Nuclear Information System (INIS)

Walczak, M.; Wojas, M.

2008-01-01

The European Network for Inspection Qualification, ENIQ, which groups the major part of the nuclear power plant operators in the European Union and in the Applicant Countries, has developed the European methodology for Qualification of Non Destructive Tests. As qualification of NDT is nowadays a standard method in the nuclear industry and in other industries. CEN (European Committee for Standardization) Technical Committee 138 '' Non Destructive Testing '' has established a Working Group, which is responsible for developing a Standard document detailing the CEN Methodology for the qualification of Non Destructive Tests applicable to all industries carrying out Non-Destructive Tests. This Standard document sets out basic principles and provides recommendations and general guidelines for carrying out qualification of NDT. It describes a methodology for qualification of Non-Destructive Tests, applicable to all NDT methods and considers qualification of equipment, procedure and personnel training. This paper presents a short background of the European Methodology for Qualification of Non-Destructive Tests and the Standard document CEN/TR 14748 '' Non-destructive testing - Methodology for qualification of non-destructive tests ''. (author)

United States nuclear tests, July 1945 through September 1992

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

Standard guide for pyrophoricity/combustibility testing in support of pyrophoricity analyses of metallic uranium spent nuclear fuel

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

1.1 This guide covers testing protocols for testing the pyrophoricity/combustibility characteristics of metallic uranium-based spent nuclear fuel (SNF). The testing will provide basic data for input into more detailed computer codes or analyses of thermal, chemical, and mechanical SNF responses. These analyses would support the engineered barrier system (EBS) design bases and safety assessment of extended interim storage facilities and final disposal in a geologic repository. The testing also could provide data related to licensing requirements for the design and operation of a monitored retrievable storage facility (MRS) or independent spent fuel storage installation (ISFSI). 1.2 This guide describes testing of metallic uranium and metallic uranium-based SNF in support of transportation (in accordance with the requirements of 10CFR71), interim storage (in accordance with the requirements of 10CFR72), and geologic repository disposal (in accordance with the requirements of 10CFR60/63). The testing described ...

Review of Nuclear Thermal Propulsion Ground Test Options

Science.gov (United States)

Coote, David J.; Power, Kevin P.; Gerrish, Harold P.; Doughty, Glen

2015-01-01

High efficiency rocket propulsion systems are essential for humanity to venture beyond the moon. Nuclear Thermal Propulsion (NTP) is a promising alternative to conventional chemical rockets with relatively high thrust and twice the efficiency of highest performing chemical propellant engines. NTP utilizes the coolant of a nuclear reactor to produce propulsive thrust. An NTP engine produces thrust by flowing hydrogen through a nuclear reactor to cool the reactor, heating the hydrogen and expelling it through a rocket nozzle. The hot gaseous hydrogen is nominally expected to be free of radioactive byproducts from the nuclear reactor; however, it has the potential to be contaminated due to off-nominal engine reactor performance. NTP ground testing is more difficult than chemical engine testing since current environmental regulations do not allow/permit open air testing of NTP as was done in the 1960's and 1970's for the Rover/NERVA program. A new and innovative approach to rocket engine ground test is required to mitigate the unique health and safety risks associated with the potential entrainment of radioactive waste from the NTP engine reactor core into the engine exhaust. Several studies have been conducted since the ROVER/NERVA program in the 1970's investigating NTP engine ground test options to understand the technical feasibility, identify technical challenges and associated risks and provide rough order of magnitude cost estimates for facility development and test operations. The options can be divided into two distinct schemes; (1) real-time filtering of the engine exhaust and its release to the environment or (2) capture and storage of engine exhaust for subsequent processing.

Helium leak testing methods in nuclear applications

International Nuclear Information System (INIS)

Ahmad, Anis

2004-01-01

Helium mass-spectrometer leak test is the most sensitive leak test method. It gives very reliable and sensitive test results. In last few years application of helium leak testing has gained more importance due to increased public awareness of safety and environment pollution caused by number of growing chemical and other such industries. Helium leak testing is carried out and specified in most of the critical area applications like nuclear, space, chemical and petrochemical industries

Terry Turbopump Expanded Operating Band Full-Scale Component and Basic Science Detailed Test Plan - Final.

Energy Technology Data Exchange (ETDEWEB)

Osborn, Douglas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Solom, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-02-01

This document details the milestone approach to define the true operating limitations (margins) of the Terry turbopump systems used in the nuclear industry for Milestone 3 (full-scale component experiments) and Milestone 4 (Terry turbopump basic science experiments) efforts. The overall multinational-sponsored program creates the technical basis to: (1) reduce and defer additional utility costs, (2) simplify plant operations, and (3) provide a better understanding of the true margin which could reduce overall risk of operations.

Nuclear energy technology: theory and practice of commercial nuclear power

International Nuclear Information System (INIS)

Knief, R.A.

1982-01-01

Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

Oxygen Containment System Options for Nuclear Thermal Propulsion Testing

Data.gov (United States)

National Aeronautics and Space Administration — All nuclear thermal propulsion (NTP) ground testing conducted in the 1950s and 1960s during the ROVER/(Nuclear Engine Rocket Vehicle Application (NERVA) program...

Non Nuclear Testing of Reactor Systems In The Early Flight Fission Test Facilities (EFF-TF)

International Nuclear Information System (INIS)

Van Dyke, Melissa; Martin, James

2004-01-01

The Early Flight Fission-Test Facility (EFF-TF) can assist in the design and development of systems through highly effective non-nuclear testing of nuclear systems when technical issues associated with near-term space fission systems are 'non-nuclear' in nature (e.g. system's nuclear operations are understood). For many systems, thermal simulators can be used to closely mimic fission heat deposition. Axial power profile, radial power profile, and fuel pin thermal conductivity can be matched. In addition to component and subsystem testing, operational and lifetime issues associated with the steady state and transient performance of the integrated reactor module can be investigated. Instrumentation at the EFF-TF allows accurate measurement of temperature, pressure, strain, and bulk core deformation (useful for accurately simulating nuclear behavior). Ongoing research at the EFF-TF is geared towards facilitating research, development, system integration, and system utilization via cooperative efforts with DOE laboratories, industry, universities, and other Nasa centers. This paper describes the current efforts for the latter portion of 2003 and beginning of 2004. (authors)

Summarisation of construction and commissioning experience for nuclear power integrated test facility

International Nuclear Information System (INIS)

Xiao Zejun; Jia Dounan; Jiang Xulun; Chen Bingde

2003-01-01

Since the foundation of Nuclear Power Institute of China, it has successively designed various engineering experimental facilities, and constructed nuclear power experimental research base, and accumulated rich construction experiences of nuclear power integrated test facility. The author presents experience on design, construction and commissioning of nuclear power integrated test facility

Basic design of radiation-resistant LVDTs: Linear Variable Differential Transformer

Energy Technology Data Exchange (ETDEWEB)

Sohn, J. M.; Park, S. J.; Kang, Y. H. (and others)

2008-02-15

A LVDT(Linear Variable Differential Transformer) for measuring the pressure level was used to measure the pressure of a nuclear fuel rod during the neutron irradiation test in a research reactor. A LVDT for measuring the elongation was also used to measure the elongation of nuclear fuels, and the creep and fatigue of materials during a neutron irradiation test in a research reactor. In this report, the basic design of two radiation-resistant LVDTs for measuring the pressure level and elongation are described. These LVDTs are used a under radiation environment such as a research reactor. In the basic design step, we analyzed the domestic and foreign technical status for radiation-resistant LVDTs, made part and assembly drawings and established simple procedures for their assembling. Only a few companies in the world can produce radiation-resistant LVDTs. Not only these are extremely expensive, but the prices are continuously rising. Also, it takes a long time to procure a LVDT, as it can only be bought about by an order-production. The localization of radiation-resistant LVDTs is necessary in order to provide them quickly and at a low cost. These radiation-resistant LVDTs will be used at neutron irradiation devices such as instrumented fuel capsules, special purpose capsules and a fuel test loop in research reactors. We expect that the use of neutron irradiation tests will be revitalized by the localization of radiation-resistant LVDTs.

Animal Effects from Soviet Atmospheric Nuclear Tests

Science.gov (United States)

2008-03-01

describes the effect on animal models of atmospheric nuclear weapons tests performed by the Soviet Union at the Semipalatinsk Test Site . Part I describes...understand the pathogenic mechanisms of injury and the likelihood of efficacy of proposed treatment measures. 15. SUBJECT TERMS Semipalatinsk Test Site ...the Semipalatinsk Test Site . Part 1 describes the air blast and thermal radiation effects. Part 2 covers the effects of primary (prompt) radiation and

Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

International Nuclear Information System (INIS)

Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye

2013-01-01

It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses

Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

Energy Technology Data Exchange (ETDEWEB)

Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses.

Dose Prediction for surface nuclear explosions: case studies for Semipalatinsk and Lop Nur tests

International Nuclear Information System (INIS)

Takada, Jun

2008-01-01

Dose prediction method RAPS after surface nuclear explosion has been developed by using the empirical dose function of USA nuclear test. This method which provides us external total dose, dose rate at any distant, at any time for any yield of nuclear explosion, is useful for radiation protection in case of nuclear events such as terrorism and nuclear war. The validity of RAPS has been confirmed by application to historical surface nuclear test explosions. The first test case study which was done for the first test explosion of the former USSR at the Semipalatinsk Nuclear Test Site on August 29th 1949, shows a good agreement with luminescence dosimetry on a brick. This dose prediction method was applied nuclear tests in Lop Nur. The results indicate dangerous nuclear radiation influences including fatal risk in the wide Uygur area. (author)

On the hydrostatic test for nuclear vessels

International Nuclear Information System (INIS)

Palmero, A.

1979-01-01

A comparison of the pressure test requirements, namely specified values of pressure and temperature, for nuclear vessels designed and constructed according to the ASME Code and Spanish Rules is presented. Also the relationship of the design criteria and the pressure test requirements is indicated with a particular emphasis on the test temperature in order to avoid brittle behaviour of the materials. (author)

Test facility for investigation of heat transfer of promising coolants for the nuclear power industry

Science.gov (United States)

Belyaev, I. A.; Sviridov, V. G.; Batenin, V. M.; Biryukov, D. A.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu.; Razuvanov, N. G.; Sviridov, E. V.

2017-11-01

The results are presented of experimental investigations into liquid metal heat transfer performed by the joint research group consisting of specialist in heat transfer and hydrodynamics from NIU MPEI and JIHT RAS. The program of experiments has been prepared considering the concept of development of the nuclear power industry in Russia. This concept calls for, in addition to extensive application of water-cooled, water-moderated (VVER-type) power reactors and BN-type sodium cooled fast reactors, development of the new generation of BREST-type reactors, fusion power reactors, and thermonuclear neutron sources. The basic coolants for these nuclear power installations will be heavy liquid metals, such as lead and lithium-lead alloy. The team of specialists from NRU MPEI and JIHT RAS commissioned a new RK-3 mercury MHD-test facility. The major components of this test facility are a unique electrical magnet constructed at Budker Nuclear Physics Institute and a pressurized liquid metal circuit. The test facility is designed for investigating upward and downward liquid metal flows in channels of various cross-sections in a transverse magnetic field. A probe procedure will be used for experimental investigation into heat transfer and hydrodynamics as well as for measuring temperature, velocity, and flow parameter fluctuations. It is generally adopted that liquid metals are the best coolants for the Tokamak reactors. However, alternative coolants should be sought for. As an alternative to liquid metal coolants, molten salts, such as fluorides of lithium and beryllium (so-called FLiBes) or fluorides of alkali metals (so-called FLiNaK) doped with uranium fluoride, can be used. That is why the team of specialists from NRU MPEI and JIHT RAS, in parallel with development of a mercury MHD test facility, is designing a test facility for simulating molten salt heat transfer and hydrodynamics. Since development of this test facility requires numerical predictions and verification

From basic nuclear data to applications

International Nuclear Information System (INIS)

Trkov, A.

2001-01-01

Reaction rates of neutron interactions with matter are parametrised by the neutron flux, which describes the neutron population and the nuclear data, which define the properties of the medium. Reaction rates determine other parameters of interest. To determine these parameters, a long chain of calculations needs to be performed. It requires on input a set of complex nuclear data and the accuracy of the calculations depends on them. To make calculations feasible, techniques have been developed to reduce the amount of information in several steps. In the lecture notes the data reduction techniques are briefly described, with emphasis on the classifications of the data resulting from individual steps. (author)

Nuclear waste repository transparency technology test bed demonstrations at WIPP

International Nuclear Information System (INIS)

Betsill J, David; Elkins, Ned Z.; Wu, Chuan-Fu; Mewhinney, James D.; Aamodt, Paul

2000-01-01

Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ''The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic

History of ground motion programs at the Nevada Test Site

International Nuclear Information System (INIS)

Banister, J.R.

1984-01-01

Some measurements were made in the atmospheric testing era, but the study of ground motion from nuclear tests became of wider interest after the instigation of underground testing. The ground motion generated by underground nuclear test has been investigated for a number of reasons including understanding basic phenomena, operational and safety concerns, yield determination, stimulation of earthquake concerns, and developing methods to aid in treaty verifications. This history of ground motion programs will include discussing early studies, high yield programs, Peaceful Nuclear Explosions tests, and some more recent developments. 6 references, 10 figures

US Underground Nuclear Test History Reports

Science.gov (United States)

History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak Atoll Cleanup Documents TRAC About Who We Are Our Values History Locations Our Leadership Director Support Center Contact Us FAQ Sheet Links Success Stories Contracts Business Opportunities Current

Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

International Nuclear Information System (INIS)

2009-01-01

On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

Report of 6th research meeting on basic process of fuel cycle for nuclear fusion reactors, Yayoi Research Group; 3rd expert committee on research of nuclear fusion fuel material correlation basis

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

In this report, the lecture materials of Yayoi Research Group, 6th research meeting on basic process of fuel cycle for nuclear fusion reactors which was held at the University of Tokyo on March 25, 1996, are collected. This workshop was held also as 3rd expert committee on research of nuclear fusion fuel material correlation basis of Atomic Energy Society of Japan. This workshop has the character of the preparatory meeting for the session on `Interface effect in nuclear fusion energy system` of the international workshop `Interface effect in quantum energy system`, and 6 lectures and one comment were given. The topics were deuterium transport in Mo under deuterium ion implantation, the change of the stratum structure of graphite by hydrogen ion irradiation, the tritium behavior in opposing materials, the basic studies of the irradiation effects of solid breeding materials, the research on the behavior of hydroxyl group on the surface of solid breeding materials, the sweep gas effect on the surface of solid breeding materials, and the dynamic behavior of ion-implanted deuterium in proton-conductive oxides. (K.I.)

Testing a CANDU-fueling machine at the Institute for Nuclear Research Pitesti

International Nuclear Information System (INIS)

Cojocaru, Virgil

2006-01-01

In 2003, as a national and European premiere, the Fueling Machine Head no. 4 (F/M) for the Nuclear Power Plant Cernavoda Unit 2 (NPP) was successfully tested at the Institute for Nuclear Research Pitesti (INR). In 2005, the second Fueling Machine (no. 5) has tested for the Nuclear Power Plant Cernavoda Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate the CANDU technology in Romania. To perform the tests of these machines at INR Pitesti, a special testing rig has built being available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing activity. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any CANDU Reactor owner

Design and construction of a basic principle simulator: an experiment

International Nuclear Information System (INIS)

Fernandez, O.; Galdoz, E.; Flury, C.; Fontanini, H.; Maciel, F.; Rovere, L.; Carpio, R.

1992-01-01

This paper describes activities developed over design and building of a Basic Principle Simulator for nuclear power plants. This simulator has been developed in Process Control Division of Bariloche Atomic Center, Argentina. This project was sponsored jointly by CNEA and Atomic Energy International Organization, through the United Nations Program for Development. The paper specially emphasizes aspects like: architecture design methodology of real time simulators; graphic environment and interfaces design for users and instructor interaction, and for display information; test and validation of the used models; and human resources formation. Finally describes the actual implementation of the simulator to be used in Embalse Nuclear Power Plant. (author)

A perspective on atomspheric nuclear tests in Nevada fact book

International Nuclear Information System (INIS)

Friesen, H.N.

1992-04-01

This Fact Book provides historical background and perspective on the nuclear testing program at the Nevada Test Site (NTS). Nuclear tests contributing to the off-site deposition of radioactive fallout are identified, and the concept of cumulative estimated exposure is explained. The difficulty of associating health effects with radiation is presented also. The status of litigation against the government and legislation (as of December 1991) are summarized

Nuclear Reactions in Micro/Nano-Scale Metal Particles

International Nuclear Information System (INIS)

Kim, Y. E.

2013-01-01

Low-energy nuclear reactions in micro/nano-scale metal particles are described based on the theory of Bose-Einstein condensation nuclear fusion (BECNF). The BECNF theory is based on a single basic assumption capable of explaining the observed LENR phenomena; deuterons in metals undergo Bose-Einstein condensation. The BECNF theory is also a quantitative predictive physical theory. Experimental tests of the basic assumption and theoretical predictions are proposed. Potential application to energy generation by ignition at low temperatures is described. Generalized theory of BECNF is used to carry out theoretical analyses of recently reported experimental results for hydrogen-nickel system. (author)

Nuclear Reactions in Micro/Nano-Scale Metal Particles

Science.gov (United States)

Kim, Y. E.

2013-03-01

Low-energy nuclear reactions in micro/nano-scale metal particles are described based on the theory of Bose-Einstein condensation nuclear fusion (BECNF). The BECNF theory is based on a single basic assumption capable of explaining the observed LENR phenomena; deuterons in metals undergo Bose-Einstein condensation. The BECNF theory is also a quantitative predictive physical theory. Experimental tests of the basic assumption and theoretical predictions are proposed. Potential application to energy generation by ignition at low temperatures is described. Generalized theory of BECNF is used to carry out theoretical analyses of recently reported experimental results for hydrogen-nickel system.

Role of testing in requalifying Transamerica Delaval, Inc., engines for nuclear service

International Nuclear Information System (INIS)

Nesbitt, J.F.; Dingee, D.A.; Laity, W.W.

1985-03-01

This paper discusses the role of testing in requalifying Transamerica Delaval, Inc. (TDI) diesel generators for use as emergency standby power sources at nuclear power plants. ''Lead'' engine tests (to confirm the design adequacy of key engine components under conditions that could induce high-cycle fatigue) and ''following'' engine tests (for engines of the same model and equipped with the same components as the ''lead'' engine) have been conducted at several nuclear power plants. The tests conducted by Duke Power Company (Catawba Nuclear Station Unit 1) and Long Island Lighting Company (Shoreham Nuclear Power Station Unit 1) are discussed. 2 refs

Testing and operation of nuclear air-cleaning systems in Qinshan NPP

International Nuclear Information System (INIS)

Yang Lin

1993-01-01

The components of nuclear air-cleaning system, system function, operational mode and the performance of cleaning components in Qinshan Nuclear Power Plant are described. The items, purpose, methods and results of in-place testing after the installation are also described in detail. The in-place testing verifies that nuclear air-cleaning systems in Qinshan Nuclear Power Plant are reliable and high effective. It also describes the points of the operational management. It is shown that the good operational management is the key which developed prescription function of nuclear air-cleaning systems. At present, Qinshan Nuclear Power Plant will be in full power, the normal operation of the system is satisfied with the demand of safe operation in Qinshan Nuclear Power Company

Nuclear Test-Experimental Science: Annual report, fiscal year 1988

Energy Technology Data Exchange (ETDEWEB)

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

1988-01-01

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

The behavior of fission products during nuclear rocket reactor tests

International Nuclear Information System (INIS)

Bokor, P.C.; Kirk, W.L.; Bohl, R.J.

1991-01-01

Fission product release from nuclear rocket propulsion reactor fuel is an important consideration for nuclear rocket development and application. Fission product data from the last six reactors of the Rover program are collected in this paper to provide as basis for addressing development and testing issues. Fission product loss from the fuel will depend on fuel composition and reactor design and operating parameters. During ground testing, fission products can be contained downstream of the reactor. The last Rover reactor tested, the Nuclear Furnance, was mated to an effluent clean-up system that was effective in preventing the discharge of fission products into the atmosphere

Development of nuclear powered ship in Japan

International Nuclear Information System (INIS)

Sato, Hiroshi

1976-01-01

The development of nuclear merchant ship in Japan was started in 1955 by the establishment of Nuclear Ship Study Group, and since then, the investigation, test and research on nuclear ships have been continued. As a result, a nuclear ocean observation and supply ship was designed for trial. Researches were carried out also in JAERI and Institute for Technical Research of Ships. Meanwhile, the nuclear icebreaker Lenin was completed in Soviet Union in 1959, the nuclear ship Savannah set out for maiden voyage in U.S. in 1962, and the construction of the nuclear ore carrier Otto Hahn was prepared in FRG. Japan Nuclear Ship Development Corp. was established in 1963, and started the design and construction of the first nuclear ship in Japan, Mutsu. The basic policy in the construction is the improvement of nuclear ship technology, the securing of safety, and the use of domestic technologies as far as possible. The progress of the design, construction and test of the Mutsu is described. Owing to the problem of radiation leak, the development of nuclear ships stagnated for a while, but the nuclear plant of the Mutsu demonstrated the expected performance in the functional test, land criticality test and zero output test, and it is expected that the bud of the independent development brought up so far can bear valuable fruit. The independent development of marine nuclear reactors should be continued by selecting the way most suitable to Japan. (Kako, I.)

78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

Science.gov (United States)

2013-05-01

... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... regulatory guide (DG), DG-1235, ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants... entitled ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants'' is temporarily...

Building Of Training Program Of Non-Destructive Testing For Concrete Structures (Part 1: Radiographic testing; Ultrasonic pulse velocity measurement; Nuclear moisture-density gauge)

International Nuclear Information System (INIS)

Nguyen Le Son; Phan Chanh Vu; Pham The Hung; Vu Huy Thuc

2007-01-01

Non-destructive testing methods (NDT) have been identified as a strong candidate for remote sensing of concrete structures over recent years. This has accelerated the powerful development of the NDT techniques in Vietnam. Hence, there is an urgent need to promote the awareness of NDT methods which could give an improved estimate of the condition concrete. Building of training program of non-destructive testing for concrete structures is a necessary duty, in aiming to build a unified training program, possibly satisfying the requirements on training as well as researching. Under the framework of the basic VAEC project (CS/07/02-03), a training program for the first 03 NDT methods: 1. Radiographic testing; 2. Ultrasonic pulse velocity measurement; 3. Nuclear moisture- density gauge was prepared. The main products of this project include: 1. Set out 03 training notes for 03 methods; 2. Set out the practical exercises to train for 03 methods; 3. Editing a set of examination questions in aiming to familiarize with various questions in 03 trained methods; 4. Fabricating practical test specimens to demonstrate for 03 techniques. (author)

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

A basic framework for the analysis of the human error potential due to the computerization in nuclear power plants

International Nuclear Information System (INIS)

Lee, Y. H.

1999-01-01

Computerization and its vivid benefits expected in the nuclear power plant design cannot be realized without verifying the inherent safety problems. Human error aspect is also included in the verification issues. The verification spans from the perception of the changes in operation functions such as automation to the unfamiliar experience of operators due to the interface change. Therefore, a new framework for human error analysis might capture both the positive and the negative effect of the computerization. This paper suggest a basic framework for error identification through the review of the existing human error studies and the experience of computerizations in nuclear power plants

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

International Nuclear Information System (INIS)

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

1992-01-01

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

The basic route of the nuclear translocation porcine growth hormone (GH)-growth hormone receptor (GHR) complex (pGH/GHR) in porcine hepatocytes.

Science.gov (United States)

Hainan, Lan; Huilin, Liu; Khan, Mahamad; Xin, Zheng; YuJiang, Yang; Hui, Zhang; Naiquan, Yao

2018-06-08

Traditional views suggest that growth hormone and the growth hormone receptor (GH/GHR complex) exert their functions only on the plasma membrane. This paradigm, however, has been challenged by recent new findings that the GH/GHR complex could translocate into cell nuclei where they could still exhibit important physiological functions. We also reported the nuclear localization of porcine GH/GHR and their potential functions in porcine hepatocytes. However, the basic path of pGH/GHR's nuclear translocation remains unclear. Combining previous research results and our current findings, we proposed two basic routes of pGH/GHR's nuclear transportation as follows: 1) after pGH binding to GHR, pGH/GHR enters into the cytoplasm though clathrin- or caveolin-mediated endocytosis, then the pGH/GHR complex enters into early endosomes (Rab5-positive), and the endosome carries the GH/GHR complex to the endoplasmic reticulum (ER). After endosome docking on the ER, the endosome starts fission, and the pGH/GHR complex enters into the ER lumen. Then the pGH/GHR complex transports into the cytoplasm, possibly by the ERAD pathway. Subsequently, the pGH/GHR complex interacts with IMPα/β, which, in turn, mediates GH/GHR nuclear localization; 2) pGH binds with the GHR on the cell membrane and, subsequently, pGH/GHR internalizes into the cell and enters into the endosome (this endosome may belong to a class of endosomes called envelope-associated endosomes (NAE)). Then, the endosome carries the pGH/GHR to the nuclear membrane. After docking on the nuclear membrane, the pGH/GHR complex fuses with the nuclear membrane and then enters into the cell nucleus. Copyright © 2018 Elsevier Inc. All rights reserved.

Revision of the second basic plans of power reactor development in Power Reactor and Nuclear Fuel Development Corporation

International Nuclear Information System (INIS)

1978-01-01

Revision of the second basic plans concerning power reactor development in PNC (Power Reactor and Nuclear Fuel Development Corporation) is presented. (1) Fast breeder reactors: As for the experimental fast breeder reactor, after reaching the criticality, the power is raised to 50 MW thermal output within fiscal 1978. The prototype fast breeder reactor is intended for the electric output of 200 MW -- 300 MW, using mixed plutonium/uranium oxide fuel. Along the above lines, research and development will be carried out on reactor physics, sodium technology, machinery and parts, nuclear fuel, etc. (2) Advanced thermal reactor: The prototype advanced thermal reactor, with initial fuel primarily of slightly enriched uranium and heavy water moderation and boiling water cooling, of 165 MW electric output, is brought to its normal operation by the end of fiscal 1978. Along the above lines, research and development will be carried out on reactor physics, machinery and parts, nuclear fuel, etc. (Mori, K

Development of non-destructive testing

International Nuclear Information System (INIS)

Park, D.Y.; Moon, Y.S.; Lim, B.K.

1980-01-01

Various standard test samples were made for eddy current test last year ('78) and several probes of eddy current test were fabricated this year ('79). The result of some basic experiments using these probes is described in this report. A EM 3300 Multitester (made by Automation Industries, U.S.A.) was purchased, which is the fundamental instrument for the examinations of steam generator U-tubes of nuclear power plant. After some necessary experiments had been performed with this instrument, we have participated in the first inservice inspection of KORI-1 nuclear power plant (Nov., '79) and accumulated much technical experiences. Some of its test results are described in this report. (author)

The consequences of underground nuclear testing in French Polynesia

International Nuclear Information System (INIS)

Brown, E.T.

1998-01-01

France began atmospheric nuclear testing at Mururoa and Fangataufa atolls in the South Pacific in July 1966. Following international protest, atmospheric testing ceased in August 1970. In late 1995, an International Geomechanical Commission (IGC) was created to assess the short- and long-term effects of underground nuclear testing on the stability and hydrology of Mururoa and Fangataufa. With the aid of its consultants, the Commission sought to develop its own understanding of the mechanics and consequences of the underground nuclear tests. It carried out extensive numerical analyses of shock wave effects, seismic wave propagation, slope stability and pre- and post-test hydrology. However, in its studies, the IGC was constrained to use the data made available to it by the French authorities. The Commission's report (International Geomechanical Commission 1998) has been submitted to the French Government. This article draws heavily on parts of that report. The Commission's observations and analyses show that there has been no apparent change, on the atoll scale, to the overall mechanical stability of either atoll as a consequence of the underground nuclear tests. The main observable consequences of the tests are underwater slope failures, open fractures on the rim surface and surface settlements. The fractures visible on the surface are generally associated with subsurface slope displacements and occur only in the carbonates. There is no evidence that slope failures or settlements have occurred in the underlying volcanics. There has been no significant change in the long-term (beyond 500 years) hydrology of either atoll. The IGC estimates that the long-term change in the natural groundwater flow will be no more than 1%. There are, however, significant short-term changes locally around the test sites, which are briefly outlined

Precompound Reactions: Basic Concepts

International Nuclear Information System (INIS)

Weidenmueller, H. A.

2008-01-01

Because of the non-zero nuclear equilibration time, the compound-nucleus scattering model fails when the incident energy exceeds 10 or 20 MeV, and precompound reactions become important. Basic ideas used in the quantum-statistical approaches to these reactions are described

Uranium: a basic evaluation

International Nuclear Information System (INIS)

Crull, A.W.

1978-01-01

All energy sources and technologies, including uranium and the nuclear industry, are needed to provide power. Public misunderstanding of the nature of uranium and how it works as a fuel may jeopardize nuclear energy as a major option. Basic chemical facts about uranium ore and uranium fuel technology are presented. Some of the major policy decisions that must be made include the enrichment, stockpiling, and pricing of uranium. Investigations and lawsuits pertaining to uranium markets are reviewed, and the point is made that oil companies will probably have to divest their non-oil energy activities. Recommendations for nuclear policies that have been made by the General Accounting Office are discussed briefly

Comprehensive Test Ban Treaty: options before nuclear Pakistan

International Nuclear Information System (INIS)

Pattanaik, Smruti S.

1998-01-01

The post-nuclear period has rendered Pakistan's strategic calculations more vulnerable. The decision to go nuclear after seventeen days of debate have started proving costly to Pakistan. This is revealed by the economic crisis resulting out of the foreign currency shortage, leading the country to default on the payment of debts. The pressure imposed by the International Monetary Fund (IMF) and World Bank and their patrons to sign the Comprehensive Test Ban Treaty (CTBT) have exposed Pakistan's economic vulnerability. Under this growing pressure, many have started questioning the decision to go nuclear

Module Testing Techniques for Nuclear Safety Critical Software Using LDRA Testing Tool

International Nuclear Information System (INIS)

Moon, Kwon-Ki; Kim, Do-Yeon; Chang, Hoon-Seon; Chang, Young-Woo; Yun, Jae-Hee; Park, Jee-Duck; Kim, Jae-Hack

2006-01-01

The safety critical software in the I and C systems of nuclear power plants requires high functional integrity and reliability. To achieve those requirement goals, the safety critical software should be verified and tested according to related codes and standards through verification and validation (V and V) activities. The safety critical software testing is performed at various stages during the development of the software, and is generally classified as three major activities: module testing, system integration testing, and system validation testing. Module testing involves the evaluation of module level functions of hardware and software. System integration testing investigates the characteristics of a collection of modules and aims at establishing their correct interactions. System validation testing demonstrates that the complete system satisfies its functional requirements. In order to generate reliable software and reduce high maintenance cost, it is important that software testing is carried out at module level. Module testing for the nuclear safety critical software has rarely been performed by formal and proven testing tools because of its various constraints. LDRA testing tool is a widely used and proven tool set that provides powerful source code testing and analysis facilities for the V and V of general purpose software and safety critical software. Use of the tool set is indispensable where software is required to be reliable and as error-free as possible, and its use brings in substantial time and cost savings, and efficiency

Basic concepts of materials accounting

International Nuclear Information System (INIS)

Markin, J.T.

1989-01-01

The importance of accounting for nuclear materials to the efficient, safe, and economical operation of nuclear facilities is introduced, and the following topics are covered: material balance equation; item control areas; material balance uncertainty; decision procedures for materials accounting; conventional and near-real-time accounting; regulatory requirements of the US Department of Energy and the Nuclear Regulatory Commission; and a summary related to the development of a materials accounting system to implement the basic concepts described. The summary includes a section on each of the following: problem definition, system objectives, and system design

Terry Turbopump Expanded Operating Band Full-Scale Component and Basic Science Detailed Test Plan-Revision 2

Energy Technology Data Exchange (ETDEWEB)

Solom, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Severe Accident Analysis Dept.; Ross, Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Severe Accident Analysis Dept.; Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Severe Accident Analysis Dept.; Osborn, Douglas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Severe Accident Analysis Dept.

2017-08-01

This document details the milestone approach to define the true operating limitations (margins) of the Terry turbopump systems used in the nuclear industry for Milestone 3 (full-scale component experiments) and Milestone 4 (Terry turbopump basic science experiments) efforts. The overall multinational-sponsored program creates the technical basis to: (1) reduce and defer additional utility costs, (2) simplify plant operations, and (3) provide a better understanding of the true margin which could reduce overall risk of operations.

The environment of the nuclear test sites on Novaya Zemlya

International Nuclear Information System (INIS)

Skorve, J.

1995-01-01

A Norwegian study of the effects of Soviet nuclear testing on the arctic island of Novaya Zemlya is underway. The study has used aerial photographs and satellite images and has revealed major rockslides and crater features that may be attributable to testing. It has been claimed that underground testing carries little risk of post-explosion contaminant release, as the explosion vitrifies and seals the surrounding rock mass. Some experts doubt the validity of this claim, and elucidation of the hydrogeological aspects of such nuclear testing is one of the aims of the study

Preliminary Nuclear Analysis for the HANARO Fuel Element with Burnable Absorber

Energy Technology Data Exchange (ETDEWEB)

Seo, Chul Gyo; Kim, So Young; In, Won Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Burnable absorber is used for reducing reactivity swing and power peaking in high performance research reactors. Development of the HANARO fuel element with burnable absorber was started in the U-Mo fuel development program at HANARO, but detailed full core analysis was not performed because the current HANARO fuel management system is uncertain to analysis the HANARO core with burnable absorber. A sophisticated reactor physics system is required to analysis the core. The McCARD code was selected and the detailed McCARD core models, in which the basic HANARO core model was developed by one of the McCARD developers, are used in this study. The development of nuclear fuel requires a long time and correct developing direction especially by the nuclear analysis. This paper presents a preliminary nuclear analysis to promote the fuel development. Based on the developed fuel, the further nuclear analysis will improve reactor performance and safety. Basic nuclear analysis for the HANARO and the AHR were performed for getting the proper fuel elements with burnable absorber. Addition of 0.3 - 0.4% Cd to the fuel meat is promising for the current HANARO fuel element. Small addition of burnable absorber may not change any fuel characteristics of the HANARO fuel element, but various basic tests and irradiation tests at the HANARO core are required.

Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

International Nuclear Information System (INIS)

Lyons, J.E.

2012-01-01

The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

Penetration Testing Model for Web sites Hosted in Nuclear Malaysia

International Nuclear Information System (INIS)

Mohd Dzul Aiman Aslan; Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Saaidi Ismail; Mohd Fauzi Haris; Norzalina Nasiruddin; Raja Murzaferi Mokhtar

2012-01-01

Nuclear Malaysia web sites has been very crucial in providing important and useful information and services to the clients as well as the users worldwide. Furthermore, a web site is important as it reflects the organisation image. To ensure the integrity of the content of web site, a study has been made and a penetration testing model has been implemented to test the security of several web sites hosted at Nuclear Malaysia for malicious attempts. This study will explain how the security was tested in the detailed condition and measured. The result determined the security level and the vulnerability of several web sites. This result is important for improving and hardening the security of web sites in Nuclear Malaysia. (author)

On the basic research of design analysis and testing based on the failure rate for pipings and equipment under earthquake conditions

International Nuclear Information System (INIS)

Shibata, H.

1980-01-01

This paper deals with the evaluation method of the failure rate of pipings and equipment of nuclear power plants under destructive earthquakes and a new design concept in this stand point of view. These researches are supported by various studies related to this subject, which have been done by the author since 1966. In this paper, the history of the development, the summaries of these studies and their significances to the practice will be described briefly. The surveys on damages of industrial facilities caused by recent destructive earthquakes are the basical study for this subject. And the continuous response observation of model structures of a plant complex to natural earthquakes is another important basic study to know the stochastic nature and significance of response analysis for the anti-earthquake design of nuclear power plants. By having the exact knowledges on these subjects, the author has been developing the evaluation procedure of the failure rate of pipings and equipment under destructive earthquake conditions, a new design method 'counter-input design' and others. Now his effort is going towards establishing their practical procedure after finishing the basic researches. (orig.)

Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part III : Radioactive Waste Management and Environment

International Nuclear Information System (INIS)

Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

2007-08-01

The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Radioactive Waste Management and Environment and there are 25 papers which have separated index. The proceedings is the third part of the three parts which published in series. (PPIN)

Japan's new basic energy plan

International Nuclear Information System (INIS)

Duffield, John S.; Woodall, Brian

2011-01-01

In June 2010, the Japanese cabinet adopted a new Basic Energy Plan (BEP). This was the third such plan that the government has approved since the passage of the Basic Act on Energy Policy in 2002, and it represents the most significant statement of Japanese energy policy in more than four years, since the publication of the New National Energy Strategy (NNES) in 2006. Perhaps more than its predecessors, moreover, the new plan establishes a number of ambitious targets as well as more detailed measures for achieving those targets. Among the targets are a doubling of Japan's 'energy independence ratio,' a doubling of the percentage of electricity generated by renewable sources and nuclear power, and a 30 percent reduction in energy-related CO 2 emissions, all by 2030. This paper explains the origins of the 2010 BEP and why it was adopted. It then describes the content of the plan and how it differs from the NNES. A third section analyzes the appropriateness of the new goals and targets contained in the BEP and their feasibility, finding that achievement of many of the targets was likely to be quite challenging even before the March 2011 earthquake, tsunami, and nuclear crisis. - Highlights: → Origins of Japan's new Basic Energy Plan. → Content of Japan's new Basic Energy Plan. → Feasibility of achieving the targets in Japan's new Basic Energy Plan. → Impact of 2011 earthquake and tsunami on Japanese energy policy.

Guidelines for inservice testing at nuclear power plants

International Nuclear Information System (INIS)

Campbell, P.

1995-04-01

The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

Basic plans of atomic energy development and utilization for fiscal 1978

International Nuclear Information System (INIS)

1978-01-01

The Government has promoted the development and utilization of atomic energy as one of the most important measures for energy supplies. In Japan, due to the unrest concerning safety of nuclear power, siting of nuclear power plants is difficult, thereby the nuclear power generation program is delayed. Then, in major research and development projects such as those of uranium enrichment, fast breeder reactors, an advanced thermal reactor and nuclear fusion, while the remarkable results are being accumulated, the practical aspects are in need of positive governmental measures. Under this situation, the long range program of atomic energy development and utilization is being revised. For the fiscal year 1978 (from April, 1978 to March, 1979), based on the revision, the basic plans are presented, first, the basic policy, and second, the practical measures: strengthening of the safety measures; establishment of the nuclear fuel cycle; development of the new types of power reactors; promotion of the basic researches; securing of the people's understanding and cooperation. (Mori, K

Research and test facilities required in nuclear science and technology

International Nuclear Information System (INIS)

2009-01-01

Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

Future Transient Testing of Advanced Fuels

Energy Technology Data Exchange (ETDEWEB)

Jon Carmack

2009-09-01

The transient in-reactor fuels testing workshop was held on May 4–5, 2009 at Idaho National Laboratory. The purpose of this meeting was to provide a forum where technical experts in transient testing of nuclear fuels could meet directly with technical instrumentation experts and nuclear fuel modeling and simulation experts to discuss needed advancements in transient testing to support a basic understanding of nuclear fuel behavior under off-normal conditions. The workshop was attended by representatives from Commissariat à l'Énergie Atomique CEA, Japanese Atomic Energy Agency (JAEA), Department of Energy (DOE), AREVA, General Electric – Global Nuclear Fuels (GE-GNF), Westinghouse, Electric Power Research Institute (EPRI), universities, and several DOE national laboratories. Transient testing of fuels and materials generates information required for advanced fuels in future nuclear power plants. Future nuclear power plants will rely heavily on advanced computer modeling and simulation that describes fuel behavior under off-normal conditions. TREAT is an ideal facility for this testing because of its flexibility, proven operation and material condition. The opportunity exists to develop advanced instrumentation and data collection that can support modeling and simulation needs much better than was possible in the past. In order to take advantage of these opportunities, test programs must be carefully designed to yield basic information to support modeling before conducting integral performance tests. An early start of TREAT and operation at low power would provide significant dividends in training, development of instrumentation, and checkout of reactor systems. Early start of TREAT (2015) is needed to support the requirements of potential users of TREAT and include the testing of full length fuel irradiated in the FFTF reactor. The capabilities provided by TREAT are needed for the development of nuclear power and the following benefits will be realized by

Future Transient Testing of Advanced Fuels

International Nuclear Information System (INIS)

Carmack, Jon

2009-01-01

The transient in-reactor fuels testing workshop was held on May 4-5, 2009 at Idaho National Laboratory. The purpose of this meeting was to provide a forum where technical experts in transient testing of nuclear fuels could meet directly with technical instrumentation experts and nuclear fuel modeling and simulation experts to discuss needed advancements in transient testing to support a basic understanding of nuclear fuel behavior under off-normal conditions. The workshop was attended by representatives from Commissariat energie Atomique CEA, Japanese Atomic Energy Agency (JAEA), Department of Energy (DOE), AREVA, General Electric - Global Nuclear Fuels (GE-GNF), Westinghouse, Electric Power Research Institute (EPRI), universities, and several DOE national laboratories. Transient testing of fuels and materials generates information required for advanced fuels in future nuclear power plants. Future nuclear power plants will rely heavily on advanced computer modeling and simulation that describes fuel behavior under off-normal conditions. TREAT is an ideal facility for this testing because of its flexibility, proven operation and material condition. The opportunity exists to develop advanced instrumentation and data collection that can support modeling and simulation needs much better than was possible in the past. In order to take advantage of these opportunities, test programs must be carefully designed to yield basic information to support modeling before conducting integral performance tests. An early start of TREAT and operation at low power would provide significant dividends in training, development of instrumentation, and checkout of reactor systems. Early start of TREAT (2015) is needed to support the requirements of potential users of TREAT and include the testing of full length fuel irradiated in the FFTF reactor. The capabilities provided by TREAT are needed for the development of nuclear power and the following benefits will be realized by the

The resumption-stopping of nuclear tests: between fear and hope

International Nuclear Information System (INIS)

Gillis, B.

1996-01-01

The situation of French deterrence, with the resumption of nuclear weapons tests until the nuclear explosions simulation with the mega joules laser and the PALEN programme, is described here. (N.C.). 1 map

Validity of a cross-specialty test in basic laparoscopic techniques (TABLT)

DEFF Research Database (Denmark)

Thinggaard, Ebbe; Bjerrum, Flemming; Strandbygaard, Jeanett

2015-01-01

. The aim of this study was to establish validity evidence for the Training and Assessment of Basic Laparoscopic Techniques (TABLT) test, a tablet-based training system. METHODS: Laparoscopic surgeons and trainees were recruited from departments of general surgery, gynaecology and urology. Participants...... included novice, intermediate and experienced surgeons. All participants performed the TABLT test. Performance scores were calculated based on time taken and errors made. Evidence of validity was explored using a contemporary framework of validity. RESULTS: Some 60 individuals participated. The TABLT...... was shown to be reliable, with an intraclass correlation coefficient of 0·99 (P value of 0·73 (P 

Hitlers' bomb. The secret story of Germanys' nuclear weapon tests

International Nuclear Information System (INIS)

Karlsch, R.

2005-01-01

This book reveals a sensation: Under supervision of the SS German scientists tested 1944/45 nuclear bombs on Ruegen and in Thuringia. During this period several hundred prisoners of war and prisoners died. Besides proofs for nuclear weapon testing the author also found a draft for a patent on plutonium bombs and discovered the first functioning German atom reactor in the environs of Berlin. (GL) [de

Republic of Lithuania law on nuclear energy. No. I-1613

International Nuclear Information System (INIS)

1996-01-01

Law on Nuclear Energy adopted by the Parliament 14 November, 1996 has the main goals of ensuring nuclear safety, peaceful use of nuclear energy and preventing from illegal use of nuclear materials. The basic assumptions of the law reinforce obligations of Lithuania under Convention on Nuclear Safety. The law determines fundamentals on nuclear energy management, principles for the state regulation for nuclear safety and radiation protection, guidelines for licensing in nuclear energy, special requirements for the design and construction of nuclear energy facilities, basic conditions for the operation of nuclear energy installations, basic requirements for the transportation and storage of nuclear and radioactive materials, basic requirements for preventing nuclear or radiation related incidents together with procedures for elimination of consequences, basic economic and financial conditions for nuclear energy and specificity of working relations in nuclear energy

Quark deconfinement in nuclei: A review of experimental tests based on nuclear magnetic moment measurements

International Nuclear Information System (INIS)

Stone, N.J.; Rikovska, J.

1988-01-01

The introduction very briefly outlines the basic idea and experimental evidence to suggest that quarks may behave differently in nuclei and in individual nucleons, with possible consequences for the calculation of nuclear magnetic dipole moments. After description of a calculation of moments made using the extreme model of total quark deconfinement (the MIT bag model) attention is focussed on experimental tests and the state of current evidence for more partial quark deconfinement. The arguments of Yamazaki which give an experimental basis for distinguishing quark deconfinement effects from, specifically, effects caused by pion exchange currents, are given in more detail. The reasons underlying choice of nuclei in which meaningful tests may be possible are given. Early claims by Karl et al. to have demonstrated the existence of quark deconfinement in mass 3 nuclei are discussed. The current status of evidence for deconfinement based on orbital g-factor measurements in heavier nuclei is also summarised. Finally some examples are given of possible experiments using recently developed on-line facilities which may provide further tests of these ideas. (orig.)

Review of nuclear pharmacy practice in hospitals

International Nuclear Information System (INIS)

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

1982-01-01

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

Ongoing research experiments at the former Soviet nuclear test site in eastern Kazakhstan

Science.gov (United States)

Leith, William S.; Kluchko, Luke J.; Konovalov, Vladimir; Vouille, Gerard

2002-01-01

Degelen mountain, located in EasternKazakhstan near the city of Semipalatinsk, was once the Soviets most active underground nuclear test site. Two hundred fifteen nuclear tests were conducted in 181 tunnels driven horizontally into its many ridges--almost twice the number of tests as at any other Soviet underground nuclear test site. It was also the site of the first Soviet underground nuclear test--a 1-kiloton device detonated on October 11, 1961. Until recently, the details of testing at Degelen were kept secret and have been the subject of considerable speculation. However, in 1991, the Semipalatinsk test site became part of the newly independent Republic of Kazakhstan; and in 1995, the Kazakhstani government concluded an agreement with the U.S. Department of Defense to eliminate the nuclear testing infrastructure in Kazakhstan. This agreement, which calls for the "demilitarization of the infrastructure directly associated with the nuclear weapons test tunnels," has been implemented as the "Degelen Mountain Tunnel Closure Program." The U.S. Defense Threat Reduction Agency, in partnership with the Department of Energy, has permitted the use of the tunnel closure project at the former nuclear test site as a foundation on which to support cost-effective, research-and-development-funded experiments. These experiments are principally designed to improve U.S. capabilities to monitor and verify the Comprehensive Test Ban Treaty (CTBT), but have provided a new source of information on the effects of nuclear and chemical explosions on hard, fractured rock environments. These new data extends and confirms the results of recent Russian publications on the rock environment at the site and the mechanical effects of large-scale chemical and nuclear testing. In 1998, a large-scale tunnel closure experiment, Omega-1, was conducted in Tunnel 214 at Degelen mountain. In this experiment, a 100-ton chemical explosive blast was used to test technologies for monitoring the

Opinion nr 2012-AV-0172 by the Nuclear Safety Authority on November 6, 2012 on the decree project authorizing the ITER international organization to create a basic nuclear installation named 'ITER' on the territory of Saint-Paul-lez-Durance (Bouches-du-Rhone)

International Nuclear Information System (INIS)

Lacoste, A.C.; Bourguignon, M.; Comets, M.P.; Dumont, J.J.; Jamet, P.

2012-01-01

This official text (published in the French 'Journal Officiel') expresses the positive opinion of the ASN about the decree project authorizing the creation of the ITER basic nuclear installation. It also contains the decree text which notably indicates the nuclear and non-nuclear buildings, presents the installation characteristics (operation limits, operation phases), and measures aiming at preventing accidents, basic safety functions (confinement control, limitation of exposure to ionizing radiation), gives an overview of measures aiming at protecting the installation against various risks (proper to the installation operation or induced by its environment), addresses issues concerning the operation (general rules, intervener training and information, protection systems, radioactive, chemical, liquid and gaseous effluents, waste management)

Task force for integral test of High Energy nuclear data

Energy Technology Data Exchange (ETDEWEB)

Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-11-01

According to completion of the JENDL-High Energy file for neutron nuclear cross sections up to 50 MeV, a task force for integral test of high energy nuclear data was organized to discuss a guide line for integral test activities. A status of existing differential and integral experiments and how to perform such a test were discussed in the task force. Here the purpose and outline of the task force is explained with some future problems raised in discussion among the task member. (author)

Durability testing of basic crystalline rocks and specification for use as road base aggregate

CSIR Research Space (South Africa)

Paige-Green, P

2007-02-01

Full Text Available , it was necessary to develop a preliminary performance ranking to assess the most appropriate material properties and test results. This was based on the observed disintegration of aggregate pieces soaked in ethylene 8 glycol combined with past testing of basic... biased towards the crushing test results as the Aggregate Crushing Value (ACV), 10% Fines Aggregate Crushing test (10%FACT) and Mod Aggregate Impact Value (AIV) are all included. In addition, six or seven different treatments are included...

Experiences with drug testing at a nuclear power plant

International Nuclear Information System (INIS)

Ray, H.B.

1987-01-01

After more than 2 yr of operation of a drug testing program at the San Onofre nuclear power plant site, the Southern California Edison Co. has had a number of experiences and lessons considered valuable. The drug testing program at San Onofre, implemented in September of 1984, continues in essentially the same form today. Prior to describing the program, the paper reviews several underlying issues that believed to be simultaneously satisfied by the program: trustworthiness, fitness and safety, public trust, and privacy and search. The overall drug testing program, periodic drug monitoring program, and unannounced drug testing program are described. In addition to the obvious features of a good drug testing program, which are described in the EEI guide, it is essential to consider such issues as the stated program rationale, employee relations, and disciplinary action measures when contemplating or engaging in drug testing at nuclear power plants

General discrimination technique to determine between earthquake and nuclear test with seismic data

International Nuclear Information System (INIS)

Bashillah Baharuddin; Alawiah Musa; Roslan Mohd Ali

2007-01-01

The Comprehensive Nuclear-Test-Ban Treaty (CTBT) was developed to ban of any nuclear weapon test explosion moreover will restrict the development and qualitative improvement of nuclear weapons and end the development of advanced new types of these weapons. The Treaty provides for a comprehensive global verification regime, which includes an International Monitoring System (IMS). The IMS comprises a network of 321 monitoring stations and 16 radionuclide laboratories that monitor the Earth for evidence of nuclear explosions, which cover underground, underwater and atmosphere environments. Presently, Malaysia receives seismic, infrasound, hydroacoustic and radionuclide data from the International Data Centre (IDC) of the CTBT. In order to maximise the use of the data for the purposes of the CTBT, the Malaysian Nuclear Agency is developing capability to analyse the data in order to detect nuclear weapon test, with an initial focus on the seismic data. Through the CTBT IMS, seismic data is constantly being obtained to monitor and detect nuclear explosions. However, in the process, other natural and man-made activities that generate seismic waves, especially earthquakes and large man-made explosions, are also detectable through the IMS, and need to be differentiated and discriminated before any nuclear explosions can be identified. The detection capability by using seismological methods was proven through simulated explosion tests at selected nuclear weapon test sites. This is supported by data previously collected from a total of 2089 nuclear weapon tests that have been carried out globally, out of which 1567 were underground, 514 in the atmosphere, including outer space, and 8 underwater. The discrimination of seismic data to detect nuclear explosions from natural earthquake and explosions can be undertaken through the identification of the epicentre location, hypocentre depth, magnitude and short-period discrimination of the seismic events. (Author)

Basics of radiation physics and instrumentation

International Nuclear Information System (INIS)

Royal, H.D.

1985-01-01

Continued technical developments are greatly changing medical diagnosis and medical care. In the field of cardiology, a number of new imaging techniques are currently available. This chapter reviews several topics that are important in the practice of nuclear cardiology. The first section discusses some of the basics of nuclear physics. Familiarity with these fundamentals is essential for an in-depth understanding of nuclear cardiology. The second section presents information on radiotracers and provides dosimetry estimates for commonly performed studies. The third section reviews the instruments used to detect radioactivity. The final section discusses computers and their applications and limitations in nuclear cardiology

Radioiodine (131I) in animal thyroids during nuclear tests in both hemispheres

International Nuclear Information System (INIS)

Van Middlesworth, L.

1975-01-01

In mid-1974 a small increase of 131 I was observed in animal thyroids following a nuclear test in China. In late 1974 there was no public announcement of an atmospheric nuclear test in the Northern Hemisphere, but 131 I was readily measured in animal thyroids. This latter increase occurred while animals in the Southern Hemisphere accumulated 131 I from nuclear tests in the Southern Hemisphere. It is suggested that in late 1974 the Northern Hemisphere was contaminated by either late fallout from tests in June or by interhemispheric mixing or by a combination of these sources. (author)

Design of high temperature Engineering Test Reactor (HTTR)

International Nuclear Information System (INIS)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio

1994-09-01

Construction of High Temperature Engineering Test Reactor (HTTR) is now underway to establish and upgrade basic technologies for HTGRs and to conduct innovative basic research at high temperatures. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 850degC for rated operation and 950degC for high temperature test operation. It is planned to conduct various irradiation tests for fuels and materials, safety demonstration tests and nuclear heat application tests. JAERI received construction permit of HTTR reactor facility in February 1990 after 22 months of safety review. This report summarizes evaluation of nuclear and thermal-hydraulic characteristics, design outline of major systems and components, and also includes relating R and D result and safety evaluation. Criteria for judgment, selection of postulated events, major analytical conditions for anticipated operational occurrences and accidents, computer codes used in safety analysis and evaluation of each event are presented in the safety evaluation. (author)

Thermoluminescence dosimetry of gamma rays from the fallout of the Semipalatinsk nuclear tests

International Nuclear Information System (INIS)

Takada, J.; Hoshi, M.; Endo, S.; Yamamoto, M.; Nagatomo, T.; Gusev, B.I.; Rozenson, R.I.; Apsalikov, K.N.; Tchaijunusova, N.J.

1996-01-01

Field missions were sent to several settlements near the Semipalatinsk nuclear test site out in order to investigate dosimetry for the residents in 1995. The results of measurements of environmental radiation doses and thermoluminescence dosimetry in some villages near the Semipalatinsk nuclear test site are presented. The radiation levels in several villages are the natural background level in 1995, 6 years after the final nuclear explosion. On the other hand, thermoluminescence dosimetry revealed significant radiation exposure to residents in this area due to nuclear tests. (author)

SP-100 nuclear assembly test: Test assembly functional requirements and system arrangement

International Nuclear Information System (INIS)

Fallas, T.T.; Gluck, R.; Motwani, K.; Clay, H.; O'Neill, G.

1991-01-01

This paper describes the functional requirements and the system that will be tested to validate the reactor, flight shield, and flight controller of the SP-100 Generic Flight System (GFS). The Nuclear Assembly Test (NAT) consists of the test article (SP-100 reactor with control devices and the flight shield) and its supporting systems. The NAT test assembly is being designed by GE. Westinghouse Hanford Company (WHC) is designing the test cell and vacuum vessel system that will contain the NAT test assembly (Renkey et al. 1989). Preliminary design reviews have been completed and the final design is under way

Nuclear strategy: India's march towards credible deterrence

International Nuclear Information System (INIS)

Sethi, Manpreet

2009-01-01

May 1998 was a momentous event in India's life. At one level, the five nuclear tests marked the culmination of the long debate on India's nuclear status. At another level, they initiated the country's journey towards credible nuclear deterrence. In the eleventh year of its existence as a state with nuclear weapons, India is engaged in a range of activities to meaningfully integrate the nuclear weapon into its national security strategy. The US and the USSR, at the same stage of their lives were engaged in pretty much a similar exercise. However, unlike the superpowers, for whom the immense destructive potential of the atomic weapon and its implications for inter-state relations suddenly burst on the scene and sent them scrambling to craft strategies that could fit the new reality, India's acquisition of nuclear weapons capability, though dictated by circumstances, came with a basic understanding of the ground rules of the game of nuclear deterrence. In fact, it may be recalled that soon after the tests, there was a spate of books and studies on India's nuclear strategy. A draft nuclear doctrine was made public just fifteen months after the tests and operational issues were beginning to be grappled with

Nuclear tests of lepton number and CP nonconservation

International Nuclear Information System (INIS)

Haxton, W.C.

1984-01-01

I will discuss two topics, double beta decay and time-reversal-odd nuclear moments, in which important questions of nuclear structure must be addressed. These problems are taken from a growing class of nuclear and atomic experiments in which the special properties of many-body systems are exploited to test properties of elementary particles. Nuclei can serve as filters for interactions by providing kinematic windows where only certain processes can occur and by isolating quantum numbers such as spin, isospin, and parity. In addition, the strengths of interesting interactions can be enhanced through the mixing of nearly degenerate levels in nuclei. However, the most important asset of nuclear and atomic experiments is their precision. For example, experiments searching for T-odd nuclear moments exploit techniques for measuring changes in atomic energies of 10 -22 eV. Such precision techniques will play an increasingly important role in particle physics. In the discussion of double beta decay and T-odd nuclear moments it will become clear that important nuclear structure issues must be resolved in order to fully exploit the experimental results. During this talk I will highlight this aspect. 29 references

Irradiation test on connector part for nuclear instrumentation of nuclear powered ship 'Mutsu'

International Nuclear Information System (INIS)

Kudo, Takahiro; Mizushima, Toshihiko; Tsunoda, Tsunemi; Nakazawa, Toshio

1991-01-01

The nuclear instrumetnation facility of the nuclear powered ship 'Mutsu' is composed of neutron detectors, signal cables and the circuits for measurement, and ocntinuously monitors neutron flux. Since this facility treats very faint signals, for the signal cables, coaxial cables and triple coaxial cables are used. The coaxial cables for the nuclear instrumentation are equipped with connectors at both ends, and those are called prefabricated cable. The prefabricated cables are connected to neutron detectors, and installed in the detection holes of the primary shielding tank in the containment vessel. Therefore, at the time of reactor operation, they are exposed to high radiation, and the deterioration of the characteristics of the prefabricated cables is feared. For the purpose of confirming that the part of deteriorating the insulation of the prefabricated cables is connectors, and clarifying the cause of the deterioration of insulation in connector part, the irradiation test of this time was carried out. The environment in which the prefabricated cables are laid, the specifications of the cables and connectors, the materials, gamma ray irradiation and the test results are reported. (K.I.)

Status of the flora and fauna on the Nevada Test Site, 1994: Results of continuing Basic Environmental Monitoring January through December 1994

International Nuclear Information System (INIS)

Hunter, R.B.

1995-09-01

This is the final progress report of a Department of Energy (DOE), Nevada operations Office (NV), program to monitor the ecology of the Nevada Test Site (NTS). The eight-year Basic Environmental Compliance and Monitoring Program (BECAMP) included meeting goals of understanding the spatial and temporal changes of plants and animals on the NTS, and determining the effects of DOE operations on those plants and animals. Determination of the changes was addressed through monitoring the most common plant and animal species at undisturbed (baseline) plots located in the major NTS valleys and mesas. One plot in Yucca Flat, the site of most nuclear weapons tests, was monitored annually, while other baseline plots were censused on a three- or four-year cycle. Effects of DOE operations were examined at sites of major disturbances, related to both DOE operations and natural disturbance mechanisms, censused on a three-year cycle. This report concentrates on work completed in 1994

Status of the flora and fauna on the Nevada Test Site, 1994: Results of continuing Basic Environmental Monitoring January through December 1994

Energy Technology Data Exchange (ETDEWEB)

Hunter, R.B. [comp.

1995-09-01

This is the final progress report of a Department of Energy (DOE), Nevada operations Office (NV), program to monitor the ecology of the Nevada Test Site (NTS). The eight-year Basic Environmental Compliance and Monitoring Program (BECAMP) included meeting goals of understanding the spatial and temporal changes of plants and animals on the NTS, and determining the effects of DOE operations on those plants and animals. Determination of the changes was addressed through monitoring the most common plant and animal species at undisturbed (baseline) plots located in the major NTS valleys and mesas. One plot in Yucca Flat, the site of most nuclear weapons tests, was monitored annually, while other baseline plots were censused on a three- or four-year cycle. Effects of DOE operations were examined at sites of major disturbances, related to both DOE operations and natural disturbance mechanisms, censused on a three-year cycle. This report concentrates on work completed in 1994.

IEEE standard for type test of class 1E electric cables, field splices, and connections for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1974-01-01

The Institute of Electrical and Electronics Engineers has generated this document to provide guidance for developing a program to type test cables, field splices, and connections and obtain specific type test data. It supplements IEEE Std 323-1974 Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations, which describes basic requirements for equipment qualification. It is the integrated performance of the structures, fluid systems, the electrical systems, the instrumentation systems of the station, and in particular, the plant protection system, that limits the consequences of accidents. Seismic effects on installed cable systems are not within the scope of this document. Section 2 of this guide is an example of type tests. It is the purpose of this guide to deal with cable and connections; however, at the time of issue, detailed examples of tests for connections were not available

Chemical Explosion Experiments to Improve Nuclear Test Monitoring - Developing a New Paradigm for Nuclear Test Monitoring with the Source Physics Experiments (SPE)

International Nuclear Information System (INIS)

Snelson, Catherine M.; Abbott, Robert E.; Broome, Scott T.; Mellors, Robert J.; Patton, Howard J.; Sussman, Aviva J.; Townsend, Margaret J.; Walter, William R.

2013-01-01

A series of chemical explosions, called the Source Physics Experiments (SPE), is being conducted under the auspices of the U.S. Department of Energy's National Nuclear Security Administration (NNSA) to develop a new more physics-based paradigm for nuclear test monitoring. Currently, monitoring relies on semi-empirical models to discriminate explosions from earthquakes and to estimate key parameters such as yield. While these models have been highly successful monitoring established test sites, there is concern that future tests could occur in media and at scale depths of burial outside of our empirical experience. This is highlighted by North Korean tests, which exhibit poor performance of a reliable discriminant, mb:Ms (Selby et al., 2012), possibly due to source emplacement and differences in seismic responses for nascent and established test sites. The goal of SPE is to replace these semi-empirical relationships with numerical techniques grounded in a physical basis and thus applicable to any geologic setting or depth

Basic research on cermet nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Ohashi, Hiroshi; Sto, Seichi [Hokkaido Univ., Sapporo (Japan). Faculty of Engineering; Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku

1998-01-01

Production of cermet nuclear fuel having fine uranium dioxide (UO{sub 2}) particles dispersed in matrix metal requires basic property data on the compatibility of matrix metal with fission product compounds. It is thermodynamically suggested that, as burnup increases, cesium in oxide fuel reacts with the fuel, other fission products or cladding pipe and produces cesium uranates, cesium molybdate, or cesium chromate in stainless steel cladding pipe. Attempt was made to measure the thermal expansion coefficient and thermal conductivity of cesium uranates (Cs{sub 2}UO{sub 4} and Cs{sub 2}U{sub 2}O{sub 7}), cesium molybdate (Cs{sub 2}MoO{sub 4}) and cesium chromate (Cs{sub 2}CrO{sub 4}). Thermal expansion was measured by X-ray diffraction and determined by Cohen`s method. Thermal conductivity was obtained by measuring thermal diffusion by laser flash method. The thermal expansion of Cs{sub 2}UO{sub 4} and Cs{sub 2}U{sub 2}O{sub 7} is as low as 1.2% for the former and 1.0% for the latter, up to 1000K. The thermal expansion of Cs{sub 2}MoO{sub 4} is as high as that of Cs{sub 2}CrO{sub 4}, 2.1% for the former and 2.5% for the latter at temperatures from room temperature to 873K. Average thermal expansion in this temperature range is 4.4 x 10{sup -5} K{sup -1} for Cs{sub 2}MoO{sub 4} and 4.2 x 10{sup -5} K{sup -1}. The thermal expansion of Cs{sub 2}CrO{sub 4} is four times higher than that of UO{sub 2} and five times higher than that of Cr{sub 2}O{sub 3}. The thermal conductivity of Cs{sub 2}UO{sub 4} is nearly equal to that of Cs{sub 2}U{sub 2}O{sub 7} in absolute value and temperature dependency. Cs{sub 2}U{sub 2}O{sub 7}, having different thermal conductivity between {alpha} and {beta} phases, shows higher conductivity with {beta} than with {alpha}, about 1/4 of that of UO{sub 2} at 1000K. The thermal conductivity of Cs{sub 2}CrO{sub 4} is nearly equal to that of Cs{sub 2}MoO{sub 4} in absolute value and temperature dependency. (N.H.)

Proceeding on the scientific meeting and presentation on basic research of nuclear science and technology (book II): chemical, waste processing technology and environment

International Nuclear Information System (INIS)

Prayitno; Syarip; Samin; Darsono; Agus Taftazani; Sudjatmoko; Tri Mardji Atmono; Dwi Biyantoro; Gede Sutresna W; Tjipto Sujitno; Slamet Santosa; Herry Poernomo; Bambang Siswanto; Eko Edy Karmanto; Endro Kismolo; Budi Setiawan; Prajitno; Jumari; Wahini Nurhayati

2015-06-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is an annual activity held by Centre for Accelerator Science and Technology, National Nuclear Energy Agency, in Yogyakarta, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings which were divided into two groups that are chemistry, environmental and waste treatment technology process . The proceedings consists of three articles from keynote speakers and 24 articles from BATAN and others participants.(PPIKSN)

Iowa Test of Basic Skills, 2000-2001. Measuring Up. E&R Report.

Science.gov (United States)

Tyler, Doris

In the Wake County Public School System (WCPSS), North Carolina, the Iowa Test of Basic Skills (ITBS) is administered to all third grade students each year. The ITBS, which is one of the assessments used as a screening tool for the Academically Gifted Program, was given to approximately 7,700 third graders in 2000. The ITBS can be given as a…

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

Safety research basic plan of JNC

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

Development of TIG Welding System for a Nuclear Fuel Test Rig

Energy Technology Data Exchange (ETDEWEB)

Joung, Changyoung; Ahn, Sungho; Hong, Jintae; Kim, Kahye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-05-15

The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers.

Development of TIG Welding System for a Nuclear Fuel Test Rig

International Nuclear Information System (INIS)

Joung, Changyoung; Ahn, Sungho; Hong, Jintae; Kim, Kahye

2013-01-01

The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers

Nuclear liability act and nuclear insurance

International Nuclear Information System (INIS)

Clarke, Roy G.; Goyette, R.; Mathers, C.W.; Germani, T.R.

1976-01-01

The Nuclear Liability Act, enacted in June 1970 and proclaimed effective October 11, 1976, is a federal law governing civil liability for nuclear damage in Canada incorporating many of the basic principles of the international conventions. Exceptions to operator liability for breach of duty imposed by the Act and duty of the operator as well as right of recourse, time limit on bringing actions, special measures for compensation and extent of territory over which the operator is liable are of particular interest. An operator must maintain $75,000,000. of insurance for each nuclear installation for which he is the operator. The Nuclear Insurance Association of Canada (NIAC) administers two ΣPoolsΣ or groups of insurance companies where each member participates for the percentage of the total limit on a net basis, one pool being for Physical Damage Insurance and the other for Liability Insurance. The Atomic Energy Control Board recommends to the Treasury Board the amount of insurance (basic) for each installation. Basic insurance required depends on the exposure and can range from $4 million for a fuel fabricator to $75 million for a power reactor. Coverage under the Operator's Policy provides for bodily injury, property damage and various other claims such as damage from certain transportation incidents as well as nuclear excursions. Workmen's Compensation will continue to be handled by the usual channels. (L.L.)

DPRK's 4{sup th} Nuclear Test and its Tritium Production

Energy Technology Data Exchange (ETDEWEB)

Kim, Min Soo; Lee, Sang Joon; Chang, Sun Young [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

On January 6, 2016 at 10:30am, the artificial earthquake in the DPRK was detected by multiple international seismic organizations. After 2 hours, the DPRK announced on state TV that 'The first H-bomb test was successfully conducted in the DPRK at 10:00 am on Wednesday, Juche 105(2016), pursuant to the strategic determination of the ruling communist party.' There has been a doubt about the real nature of the DPRK's 4th nuclear test, since 2 months have been passed after its nuclear test. To analyze the nature of the DPRK's nuclear test, it is necessary to check possible options for production of essential materials. The pathways to produce nuclear fusion material (tritium) and to have a relatively high possibility for the DPRK are described in this article. Tritium is key material for H-bomb. And there are two options for the DPRK which are 1) production and 2) illicit trafficking. And this study is focused on production possibility of DPRK. Determination of the nature of DPRK's nuclear test is very hard issue.

Nuclear start-up, testing and core management of the Fast Test Reactor (FTR)

International Nuclear Information System (INIS)

Bennett, R.A.; Daughtry, J.W.; Harris, R.A.; Jones, D.H.; Nelson, J.V.; Rawlins, J.A.; Rothrock, R.B.; Sevenich, R.A.; Zimmerman, B.D.

1980-01-01

Plans for the nuclear start-up, low and high power physics testing, and core management of the Fast Test Reactor (FTR) are described. Owing to the arrangement of the fuel-handling system, which permits continuous instrument lead access to experiments during refuelling, it is most efficient to load the reactor in an asymmetric fashion, filling one-third core sectors at a time. The core neutron level will be monitored during this process using both in-core and ex-core detectors. A variety of physics tests are planned following the core loading. Because of the experimental purpose of the reactor, these tests will include a comprehensive characterization programme involving both active and passive neutron and gamma measurements. Following start-up tests, the FTR will be operated as a fast neutron irradiation facility, to test a wide variety of fast reactor core components and materials. Nuclear analyses will be made prior to each irradiation cycle to confirm that the planned arrangement of standard and experimental components satisfies all safety and operational constraints, and that all experiments are located so as to achieve their desired irradiation environment. (author)

Nondestructive testing of nuclear reactor components integrity

International Nuclear Information System (INIS)

Mala, M.; Miklos, M.

2011-01-01

Nuclear energy must respond to current challenges in the energy market. The significant parameters are increase of the nuclear fuel price, closed fuel cycle, reduction and safe and the final disposal of high level radioactive waste. Nowadays, the discussions on suitable energy mix are taking place not only here in Czech Republic, but also in many other European countries. It is necessary to establish an appropriate ratio among the production of electricity from conventional, nuclear and renewable energy sources. Also, it is necessary to find ways how to streamline the economy, central part of the nuclear fuel cycle and thereby to increase the competitiveness of nuclear energy. This streamlining can be carried out by improving utilization of existing nuclear fuel with maintaining a high degree of nuclear facilities safety. Increasing operational reliability and safety together with increasing utilization of nuclear fuel place increasing demands on monitoring of changes during fuel burnup. The potential fuel assembly damages in light water reactors are prevented by the introduction of new procedures and programs of the fuel assembly monitoring. One of them is the Post Irradiation Inspection Program (PIIP) which is a good tool for monitoring of chemical regime impact on the fuel assembly cladding behavior. Main nondestructive techniques that are used at nuclear power plants for the fuel assembly integrity evaluation are ultrasonic measurements, eddy current measurements, radiographic testing, acoustic techniques and others. Ultrasonic system is usual tool for leak fuel rod evaluation and it is also used at Temelin NPP. Since 2009, Temelin NPP has cooperated with Research Center Rez Ltd in frame of PIIP program at both units WWER 1000. This program was established for US VVantage6 fuel assemblies and also it continues for Russian TVSA-T fuel assemblies. (author)

Concerning 1991 basic plan for atomic energy development and application (subjected to examination)

International Nuclear Information System (INIS)

1990-01-01

The prime minister developed a draft 1991 Basic Plan for Atomic Energy Development and Application and sent it to the Nuclear Safety Commission for examination. The Commission started the examination at its 14th meeting. The report outlines results of the examination. A Basic Plan is developed each year to promote efforts at atomic energy development and application systematically and efficiently. In particular, it identifies specific activities required to realize the basic policies shown in the Long Term Program for Atomic Energy Development and Application. In the present report, activities required for improving the safety measures in general are described first, with special emphasis placed on the improvement in nuclear safety regulations and promotion of nuclear safety research. Activities required for promoting nuclear power generation are then outlined. It also insists that the nuclear fuel cycle should be established by promoting measures for uranium resources, uranium enrichment, spent fuel enrichment, and radioactive waste disposal. Other required efforts include the development of improved power reactors, implementation of major projects, and development of basic technology. (N.K.)

Development of standard testing methods for nuclear-waste forms

International Nuclear Information System (INIS)

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

1981-11-01

Standard test methods for waste package component development and design, safety analyses, and licensing are being developed for the Nuclear Waste Materials Handbook. This paper describes mainly the testing methods for obtaining waste form materials data

Testing techniques in nuclear, petroleum and metallurgic industries

International Nuclear Information System (INIS)

Anon.

1977-01-01

The nondestructive testing techniques by ultrasonic waves, eddy currents, acoustic emission used by Intercontrole (a CEA's affiliated firm in nuclear petrochemical, and engineering site measurements) are presented [fr

Two CANDU fueling machines tested at the Institute For Nuclear Research - Pitesti

International Nuclear Information System (INIS)

Doca, Cezar; Cojocaru, Virgil

2005-01-01

In 2003, as a national and European premiere, at the Institute for Nuclear Research Pitesti (INR), the Fueling Machine Head no.4 (F/M) for the Nuclear Power Plant Cernavoda - Unit 2 was successfully tested. In 2005, a second Fueling Machine (no.5) was tested for the Nuclear Power Plant Cernavoda - Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate in Romania the CANDU technology. To perform the tests of these machines at INR Pitesti, a special testing rig was built and is available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing operation. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any other CANDU Reactor owner. This experience will support the next steps concerning F/M commissioning in the NPP Cernavoda - Unit 2 and also give the confidence to the end-users that the Institute's team can provide technical assistance during the operation. Also, the obtained results demonstrate that the overall refurbishment of the F/M control system in Unit 1 and Unit 2 will be possible. The paper presents: - a short description of the F/M head;- a short description of the F/M test rig; - the computer control system; - the F/M testing activities; -results and expectations. (authors)

Two CANDU fueling machines tested at the Institute For Nuclear Research - Pitesti

International Nuclear Information System (INIS)

Doca, C.; Cojocaru, V.

2005-01-01

Full text: In 2003, as a national and European premiere, at the Institute for Nuclear Research Pitesti (INR), the Fueling Machine Head no.4 (F/M) for the Nuclear Power Plant Cernavoda - Unit 2 was successfully tested. In 2005, a second Fueling Machine (no.5) was tested for the Nuclear Power Plant Cernavoda - Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate in Romania the CANDU technology. To perform the tests of these machines at INR Pitesti, a special testing rig was built and is available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing operation. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any other CANDU Reactor owner. This experience will support the next steps concerning F/M commissioning in the NPP Cernavoda - Unit 2 and also give the confidence to the end-users that the Institute's team can provide technical assistance during the operation. Also, the obtained results demonstrate that the overall refurbishment of the F/M control system in Unit 1 and Unit 2 will be possible. The paper presents: - a short description of the F/M head;- a short description of the F/M test rig; - the computer control system; - the F/M testing activities; -results and expectations. (authors)

Determination of discharge authorizations for French basic nuclear installations 58 and public information

International Nuclear Information System (INIS)

Tabard, Laurence; Conte, Dorothee

2013-01-01

The determination of discharge authorized limits for a French nuclear site is initiated by the request of the operator, based on the maximum nuclear and chemical inventory that could be released during normal operating conditions, accompanied with justifications. Request and justifications are analyzed and discussed by the ASN and the IRSN, taking into account nuclear and chemical inventories expected inside BNI, current regulations (BNI specific regulation, environment code, public health code), operating feedback (release feedback for an operating BNI, feedback coming from other nuclear sites or installations, etc.) and best available technologies that can be used to treat liquid or gaseous waste before release. After taking into account potential suggestions coming from public information or public enquiry concerning the operator request, the discharge authorized limits are settled down in specific ASN prescriptions that have to be ratified by the State secretaries in charge of nuclear safety. The whole process runs through 2 or 3 years to be achieved. Communication has revealed to be quite an uneasy task, even for administrative procedures. This aspect is mostly tested while communicating about events. Consequences of this communication can hardly be foreseen because of multiple external parameters like: news on the front pages at the same moment; historic communication difficulties still in the public mind; technical vocabulary not easily understood; public fear of things being hidden; power of ecologist or non-governmental associations. (authors)

Criticality Safety Basics for INL FMHs and CSOs

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

2012-04-01

Nuclear power is a valuable and efficient energy alternative in our energy-intensive society. However, material that can generate nuclear power has properties that require this material be handled with caution. If improperly handled, a criticality accident could result, which could severely harm workers. This document is a modular self-study guide about Criticality Safety Principles. This guide's purpose it to help you work safely in areas where fissionable nuclear materials may be present, avoiding the severe radiological and programmatic impacts of a criticality accident. It is designed to stress the fundamental physical concepts behind criticality controls and the importance of criticality safety when handling fissionable materials outside nuclear reactors. This study guide was developed for fissionable-material-handler and criticality-safety-officer candidates to use with related web-based course 00INL189, BEA Criticality Safety Principles, and to help prepare for the course exams. These individuals must understand basic information presented here. This guide may also be useful to other Idaho National Laboratory personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. This guide also includes additional information that will not be included in 00INL189 tests. The additional information is in appendices and paragraphs with headings that begin with 'Did you know,' or with, 'Been there Done that'. Fissionable-material-handler and criticality-safety-officer candidates may review additional information at their own discretion. This guide is revised as needed to reflect program changes, user requests, and better information. Issued in 2006, Revision 0 established the basic text and integrated various programs from former contractors. Revision 1 incorporates operation and program changes implemented since 2006. It also incorporates suggestions, clarifications

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-01

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

Dynamic testing of nuclear power plant structures: an evaluation

International Nuclear Information System (INIS)

Weaver, H.J.

1980-02-01

Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants

Methods for in-place testing of HEPA and iodine filters used in nuclear power plants

International Nuclear Information System (INIS)

Holmberg, R.; Laine, J.

1978-04-01

The purpose of this work was a general investigation of existing in-place test methods and to build an equipment for in-place testing of HEPA and iodine sorption filters. In this work the discussion is limited to methods used in in-place testing of HEPA and iodine sorption filters used in light-water-cooled reactor plants. Dealy systems, built for the separation of noble gases, and testing of them is not discussed in the work. Contaminants present in the air of a reactor containment can roughly be diveded into three groups: aerosols, reactive gases, and noble gases. The aerosols are filtered with HEPA (High Efficiency Particulate Air) filters. The most important reactive gases are molecular iodine and its two compounds: hydrogen iodide and methyl iodide. Of gases to be removed by the filters methyl iodide is the gas most difficult to remove especially at high relative humidities. Impregnated activated charcoal is generally used as sorption material in the iodine filters. Experience gained from the use of nuclear power plants proves that the function of high efficiency air filter systems can not be considered safe until this is proved by in-place tests. In-place tests in use are basically equal. A known test agent is injected upstream of the filter to be tested. The efficiency is calculated from air samples taken from both sides of the filter. (author)

Ecology and basic laws

International Nuclear Information System (INIS)

Mayer-Tasch, P.C.

1980-01-01

The author sketches the critical relation between ecology and basic law - critical in more than one sense. He points out the incompatibility of constitutional states and atomic states which is due to constitutional order being jeopardised by nuclear policy. He traces back the continuously rising awareness of pollution and the modern youth movement to their common root i.e. the awakening, the youth movement of the turn of the century. Eventually, he considers an economical, political, and social decentralization as a feasible alternative which would considerably relieve our basic living conditions from the threatening forms of civilization prevailing. (HSCH) [de

Basic plan for nuclear power development and utilization in 1987

International Nuclear Information System (INIS)

1987-01-01

This report presents specific measures to be carried out in 1987 to promote research, development and application of nuclear power. The first part deals with the strengthening of safety measures, centering on the improvement in regulation and administration for nuclear power safety; promotion of safety studies; improvement and strengthening of disaster prevention measures; improvement and strengthening of environmental activity surveys; improvement in exposure control measures for nuclear power operation workers; and establishment of the nuclear fuel cycle and safety in such activities as development of new reactors. The second part of the report addresses the promotion of nuclear power generation. Measures for this will be focused on the promotion of location of nuclear power plants and the development of advanced technology for light water reactors. The third part describes measures for establishing the nuclear fuel cycle, which cover the procurement of uranium resources; enrichment of uranium; reprocessing of spent fuel and utilization of plutonium and recovered uranium; and disposal of radioactive waste. Other parts presents measures to be carried out for the development of new power reactors; research on nuclear fusion; development of nuclear powered vessels; application of radiations; improvement in the infrastructure for nuclear power development and utilization; etc. (Nogami, K.)

Study on the seismic monitoring system development against the adjacent countries nuclear test

International Nuclear Information System (INIS)

Min, Kyung Sik; Ahn, Jong Sung; Lee, Jong Wook; Chang, In Soon; Seo, In Seok; Kwak, Eun Ho

1995-12-01

The project was carried out to construct foundation for the monitoring of the neighboring countries's nuclear test by seismic method. For this, we collected, organized and analyzed the information about the Comparative Test Ban Treaty (CTBT) and investigated theoretical backgrounds of the elastic wave generation by the Nuclear test and the identification of the nuclear tests from the natural earthquakes. And the computer system was setup to obtain realtime data from the broadband seismograph in Inchon of the Korean Meteorological Agency. 15 refs. (Author)

Nuclear weapon testing and the monkey business

International Nuclear Information System (INIS)

Murthy, M.S.S.

1978-01-01

Reasons for India's total ban on the export of rhesus monkeys to U.S. have been explained. The major reason is that some of the animals were used in nuclear weapon related radiation experiments. This was a clear violation of a stricture in the agreement about supply of monkeys. The stricture prohibited the use of animals for research concerning military operations, including nuclear weapon testing. It is pleaded that a strict enforcement of strictures rather than a total ban on the export of monkeys would be better in the interest of advancement of knowledge in human medicine and disease control. (M.G.B.)

Nuclear test watchers feel political heat

International Nuclear Information System (INIS)

Marshall, E.

1987-01-01

One year after US citizen diplomats signed a remarkable pact with the Soviet Union to monitor nuclear bomb tests, they are running into some of the obstacles that regular diplomats encounter - political flak from the Pentagon and harassment by the Soviet military. But they have devised some technical solutions that they hope will get them around the roadblocks. These solutions are discussed

Nuclear design and technical development required for ISER plant

International Nuclear Information System (INIS)

Yokoyama, Takashi; Yamano, Naoki.

1987-01-01

The report outlines some results of a study carried out by the ISER (intrinsically safe and economical reactor) Investigation Group. In particular, nuclear design concepts are examined in relation to the fuel cycle. Discussion is also made on technical development efforts to be made for realizing an ISER. Calculation of some basic nuclear design parameters is performed and results are used to examine the reactor core and fuel for ISER. As a result, it is indicated that a high-burnup type reactor core should be used on a 4.5-batch replacement, 15 EFPM (effective full power month) scheme to optimize an ISER. For technical development, consideration is made on various tests to be performed with an experimental reactor, called ISER-E, as well as other tests to provide basic data required for demonstrating the inherent safety of ISER. The study also deals with the possibility of the application of currently available light water reactor techniques to experiments with a critical assembly, non-nuclear test loop, and the experimental reactor ISER-E. It is revealed that many of the required experiments can be carried out by using test facilities and light water reactor techniques which are currently, or will be readily, available. It is stressed that international cooperation is necessary to accomplish these tests. (Nogami, K.)