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Bioux, P.; Mouney, H.; Rowlands, J.L.
Electricite de France (EDF), 92 - Clamart (France)
Electricite de France (EDF), 92 - Clamart (France)
AbstractAbstract
[en] Activity in the field of nuclear data for the fission power technology applications is reviewed. The present situation is of concern to the French nuclear industry because of the few measurement facilities which are now funded for work in the field and the reductions in the number of scientists expert in measurement and evaluation of nuclear data. It is argued that there are requirements which justify work to improve many items of nuclear data. (authors)
Original Title
Situation actuelle en matiere de mesures et d'evaluation de donnees nucleaires pour les applications aux reacteurs de puissance a fission
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May 1994; 7 p
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Report
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[en] Because of the high seismicity of the West Java area, the MPR research reactor is being designed to withstand a major earthquake. The dynamic model used in the design of the reactor is described
Original Title
Seismic design of the MPR-30 research reactor, Serpong, West Java
Primary Subject
Source
Vogt, E.W.; Ludgate, G.A. (TRIUMF, Vancouver, BC (Canada)) (eds.); Canadian Nuclear Association, Toronto, ON (Canada); 388 p; ISBN 0-919307-30-2;
; 1983; p. 217-220; 4. Pacific Basin nuclear conference; Vancouver, BC (Canada); 11-15 Sep 1983

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Miscellaneous
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AbstractAbstract
[en] This Standard identifies the elements of an emergency plan which describes the approach to coping with emergencies and minimizing the consequences of accidents at research reactor facilities. The emphasis given each of these elements shall be commensurate with the potential risk involved. The emergency plan shall be implemented by emergency procedures
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1983; 7 p; American Nuclear Society; La Grange Park, IL (USA); ANSI/ANS--15.16-1982
Record Type
Book
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Standard
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AbstractAbstract
[en] Emergency action level (EAL) technical criteria or parameters for emergency conditions classes. Reference methodology for development of EAL in foreign countries, in process of developed and reviewed emergency plan of home several research reactors, the author thought that should be taken initiating conditions which result in emergency conditions quantified some instrumental readings or alarm thresholds, in order to distinguish and confirm emergency conditions and provide technical bases for emergency response actions. Then based on this principle, revised or developed emergency plans of INET Tsinghua University, promote development of work for emergency plan of research reactors
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Journal Article
Journal
Nuclear Power Engineering; ISSN 0258-0926;
; v. 21(3); p. 213-215, 220

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AbstractAbstract
[en] Research reactor personnel operate the reactor and carry out the experiments. These two types of work entail different activities, and therefore different skills and competence, the number of relevant staff being basically a function of the size, complexity and versatility of the reactor. Training problems are often reactor-specific, but the present paper considers them from three different viewpoints: the training or retraining of new staff or of personnel already employed at an existing facility, and training of personnel responsible for the start-up and operation of a new reactor, according to whether local infrastructure and experience already exist or whether they have to be built up from scratch. On-the-spot experience seems to be an essential basis for sound training, but requires teaching abilities and aids often difficult to bring together, and the availability of instructors that does not always fit in smoothly with current operational and experimental tasks. (author)
Original Title
Formation du personnel des reacteurs de recherche
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; p. 609-613; ISBN 92-0-050080-3;
; 1980; p. 609-613; IAEA; Vienna; International symposium on manpower requirements and development for nuclear power programmes; Saclay, France; 2 - 6 Apr 1979; IAEA-SM--238/30

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Book
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[en] A description and a survey of the main specifications of the Budapest Polytechnical University training reactor are given. The significance is assessed of the reactor for training and scientific purposes and the main tasks are outlined using the reactor in the fields of reactor physics and neutron activation analysis. (B.S.)
Original Title
Skolni reaktor technicke univerzity v Budapesti
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Journal Article
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Jaderna Energie; v. 24(8); p. 312-317
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Guinn, V.P.
California Univ., Irvine (USA). Dept. of Chemistry
California Univ., Irvine (USA). Dept. of Chemistry
AbstractAbstract
[en] This study was carried out to assess the present degree of utilization of research-type nuclear reactors in a number of developing Asian and Latin American countries - and the various factors that appear to be either stimulating or inhibiting their optimum utilization. In addition, the study included less-detailed assessments of various other related nuclear programs in these countries. The report is based primarily upon observations made by the author during a number of scientific meetings in which he participated in these geographical areas, and during a number of trips he made to a number of these countries for discussions concerning their degree of reactor utilization (and related subjects)
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Dec 1975; 66 p; Available from NTIS. $4.50.
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Bae, Sang Hoon; Baang, Dane; Park, Gee Yong; Choi, Young San; Kim, Young Ki
Proceedings of the KNS autumn meeting
Proceedings of the KNS autumn meeting
AbstractAbstract
[en] In a research reactor, a CAR(Control Absorber Rod) interface module which receives the control information from the RRS(Reactor Regulating System) control computer and transfer control signal to a step motor in a CAR has been composed of an interface card, an indexer card and a driver card. Due to such separated interface components, the additional interface for each component was inevitable. That is, a CAR interface was more complicated and its corresponding communication ports, drivers and signal cables were unnecessarily required. To simplify this stuff, the interface card and indexer card are integrated to one module and integrated communication network including a step motor driver card can be established through backplane network. The CAR interface module has not been redundant because power operation excluding a CAR by a failure in CAR could be available thanks to remained CARs. But, actually in spite of one CAR failure, operation with remained CARs normally is likely impossible to keep track of rapid dynamics. To solve this problem, the modular redundant structure is introduced herein and this method will let us anticipate the high reliability
Primary Subject
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Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2011; [2 p.]; 2011 autumn meeting of the KNS; Kyoungju (Korea, Republic of); 26-28 Oct 2011; Available from KNS, Daejeon (KR); 2 refs, 2 figs
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[en] Research reactors should incorporate the measurement system for the core power to control and regulate the reactor power. The research reactor modeled in this paper is also equipped with three separate and independent detectors to measure the core power; Neutron Measurement System (NMS), Reactor Gamma Monitoring System (RGMS) and Primary coolant Gamma Monitoring System (PGMS). To calibrate these detectors, the thermal power is used as calibration reference. Therefore, it should be ensured that the thermal power be defined to be fully representative of the core power. The thermal power is calculated based on the thermal balance in the reactor pool where the reactor core and heavy water vessel as the heat source are located. In this paper, the calculation logic for the thermal power is explained in detailed and the precautions for calibration are introduced as well. The equation for the core thermal power has been derived according to measuring parameters such as mass flow rate, and temperatures. In addition, the precautions for calibration such as calibration sequence and pool water effect are clarified as well.
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Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2017; [2 p.]; 2017 Fall Meeting of the KNS; Kyungju (Korea, Republic of); 25-27 Oct 2017; Available from KNS, Daejeon (KR); 1 ref, 1 fig
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Miscellaneous
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[en] In the last 60 years, the scientists spent tens of billion dollars attempting to develop useful thermonuclear energy. But they cannot yet reach a stable thermonuclear reaction. They still are promising publicly, after another 15-20 years, more tens of billions of US dollars to finally design the expensive workable industrial installation. The author offers a new, small, cheap cumulative inertial thermonuclear reactor, which increases the pressure and temperature of its nuclear fuel thousands of times, reaches the required ignition stage and, ultimately, full constant contained thermonuclear reaction. Cumulative reactor contains several innovations to achieve its product. It is safe and ecological. The author is aware that no cumulative pressure research was done anywhere else in the world, especially with additional rocket acceleration. The chief among them is using moving explosives (rocket thrust), which allows to accelerate the special piston to a very high speed (more 30 km/s) which (as it is shown by integral computations) compresses the fuel capsule a million times and heats up million degrees of temperature. The author gives detailed computations of the Lawson criterion. He shows the current conventional inertial laser method gives only 0.28 < 1 of the needed Lawson criterion of thermonuclear reaction (ρR > 1 g/cm2). The offered method gives 585 > 1 of the needed Lawson criterion. The proposed method cannot only achieve but also significantly exceed the Lawson criterion. The experimental reactor is about a thousand times cheaper than a typical laser unit.
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Journal Article
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Energy, Sustainability and Society (Online); ISSN 2192-0567;
; v. 6(1); p. 1-16

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