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Journal Article
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Nuclear Science and Engineering; v. 49(3); p. 358-369
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No abstract available
Original Title
Das integrierte Regelsystem der BBR-Reaktoranlage
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Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 518-520; 1973; ZAED; Leopoldshafen, F.R. Germany; Reactor meeting; Karlsruhe, F.R. Germany; 10 Apr 1973; 2 figs. Short communication only.
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Book
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Conference
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No abstract available
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Ein Beitrag zur optimalen Xenonregelung grosser Leistungsreaktoren
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Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 197-200; 1973; ZAED; Leopoldshafen, F.R. Germany; Reactor meeting; Karlsruhe, F.R. Germany; 10 Apr 1973; 1 fig.; 1 ref. Short communication only.
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Book
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AbstractAbstract
No abstract available
Original Title
Fortschritte in der Rauschanalyse zur betriebsmaessigen Ueberwachung von Druckwasserreaktoren
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Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 478-481; 1973; ZAED; Leopoldshafen, F.R. Germany; Reactor meeting; Karlsruhe, F.R. Germany; 10 Apr 1973; 7 figs.; 6 refs. Short communication only.
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Book
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AbstractAbstract
[en] Under European regional TC project RER/4/011, IAEA and VUJE Training centre organized a workshop on On-line Testing of Nuclear Power Plant Temperature and Pressure Instrumentation and Other Critical Plant Equipment in Trnava, Slovak Republic, from 25 to 29 May 1998. The objective of the workshop was to review the state-of-the-art in NPP instrumentation, cover typical instrumentation problems and solutions, describe technical and regulatory requirements for verifying the performance of nuclear power plant instrumentation, describe new methods developed and applied in NPPs for on-line verification and performance of instrumentation and present new techniques using existing instrumentation to identify the on-set problems in the plant electrical, mechanical and thermal hydraulic systems. Particular emphasis was placed on temperature measurements by Resistance Temperature Detectors (RTDs) and thermocouples and pressure measurements using motion-balanced and forced-balanced pressure transmitters. This proceedings includes papers presented by the invited speakers and the participants each with an abstract as wells as a summary of the Round-Table discussions
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Source
1998; 609 p; IAEA; Vienna (Austria); IAEA regional workshop on on-line testing of nuclear plant temperature and pressure instrumentation and other critical plant equipment; Trnava (Slovak Republic); 25-29 May 1998; PROJECT RER/4/011-05/98; Refs, figs, tabs
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Miscellaneous
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[en] The mission of the World Association of Nuclear Operators (WANO) is highlighted, and WANO's Peer Review programme is described. At the Dukovany nuclear power plant, a Peer Review was undertaken in December 1997. The results gave evidence of a good level of safety, reliability and culture of operation of the plant. (P.A.)
Original Title
Mezinarodni spoluprace - cesta ke zlepsovani spolehlivosti a bezpecnosti
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Source
Faculty of Nuclear Science and Physical Engineering, Czech Technical University, Prague (Czech Republic); [104 p.]; Oct 1998; p. 35; Nukleonika '98; Prague (Czech Republic); 9-10 Sep 1998
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Miscellaneous
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Adachi, Takeo; Itoh, Mitsuo; Yamaguchi, Hitoshi
Japan Atomic Energy Research Inst., Tokyo (Japan)1998
Japan Atomic Energy Research Inst., Tokyo (Japan)1998
AbstractAbstract
[en] Exhaust ducts 2F and 3F of Research Building No.4 was renewed by replacing old steel ducts lining with vinyl chloride to hard type vinyl chloride ducts. Following the preparation works from July 1997, the construction was started at the beginning of December 1997 and finished at the end of April 1998. Before the construction, a working group consisting of the facility manager, the manager for radiation protection and the representative users of the facility was organized in order to discuss various things concerning the construction such as plans, specifications and so on. All of the management works during construction was done by the working group. In this paper, the renewal of exhaust ducts inside the radiation controlled area (Research Building No.4) is described. (author)
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Source
Dec 1998; 54 p
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Report
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Kondoh, Y.; Motomura, A.
Specialists meeting on design and assessment of instrumentation and control systems in NPP coping with rapid technological change1998
Specialists meeting on design and assessment of instrumentation and control systems in NPP coping with rapid technological change1998
AbstractAbstract
[en] Digital technology is being applied to control systems in nuclear power plants. Especially in Japanese BWRs, control systems are being digitized both in constructing plant and in retrofit of operating plants. Digital technology has many advantages compared with analog technology. However, its high performance and flexibility may result in too complicated software structure, which will cause long design time and long testing time and increase cost. In introduction of digital technology, it is most important to restrict unnecessary flexibility of software. The function of control systems can be divided in standard part and variable part. Standard function may be common to every plant while variable function should be designed for each plant. Even in current design, standard design is preserved to be reused in next application. However, this design approach is not always effective because standard function may be changed by customer and nothing is considered for variable part even if it is large. To keep reliability and reduce cost by software reuse, Toshiba adopts modular design of control software, where standard part is designed as a set of standard functional modules and variable function is designed as a complex of standard functional modules and plant unique modules. Toshiba firstly applied modular design method to fuel handling machine control system. In this application the design work has been reduced to 30 percent by reusing of functional module which was first developed in former applications. This remarkable reduction of design work has enhanced reliability with less cost. In addition, software, has been produced and tested according to the functional module. These qualified software modules will be applied to next system and will realize highest reliability and least cost. Toshiba is now planning the application of this modular design method for every digital control system. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Institut fuer Sicherheitstechnologie (ISTec) GmbH, Garching (Germany); 188 p; Oct 1998; p. 63-68; Specialists meeting on design and assessment of instrumentation and control systems in NPP coping with rapid technological change; Garching (Germany); 6-8 Oct 1998; 4 figs
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Report
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Kucharek, P.
Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material1998
Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material1998
AbstractAbstract
[en] Since foundation of Nuclear Power Plant Research Institute (NPPRI) in 1977, the department of diagnostics has been dealt with problems related to the theoretical, practical and organizatory questions of operational diagnostics connected with PWR type nuclear components. This department acts directly in locality of NPP Jaslovske Bohunice, but there are performances for all NPP in Slovak or Czech Republic (Dukovany, Mochovce, and Temelin). Besides direct services and achievements for NPP there exist advisory, experts and research activities for the government and supervising authorities, too. In 1985, NPPRI began systematically construct and verify technical means for operational diagnostics of main circulating pumps (MCP) with good results, based on own rich practical experiences and contacts with organisations abroad. In recent years NPPRI as one of recognised qualified and authorised institutions in Slovak Republic has begun to develop a new generation of diagnostic systems for NPP on high technical level but with lower procuring costs in comparison with western countries products. This contribution deals with four following types of diagnostic systems which were not only developed but also delivered and installed on Slovak and Czech nuclear units: - Loose part monitoring system (LPMS), - Humidity monitoring system (HUMON), - Reactor coolant pumps monitoring system (RCPMS), - Primary circuit vibration monitoring system (VMS). Main features of new generation from middle of 1990's of these systems are described in this paper and operational experiences with them too. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Turkish Atomic Energy Agency, Ankara (Turkey); 214 p; 1998; p. 25-34; Technical committee meeting on diagnostic systems in nuclear power plants; Istanbul (Turkey); 22-24 Jun 1998; 4 figs
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Report
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Sohn, SeDo; Shin, HyunKook; Han, JaiBok
International symposium on evolutionary water cooled reactors: strategic issues, technologies and economic viability. Book of extended synopses1998
International symposium on evolutionary water cooled reactors: strategic issues, technologies and economic viability. Book of extended synopses1998
AbstractAbstract
No abstract available
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Source
International Atomic Energy Agency, Vienna (Austria); Korea Electric Power Corporation, Seoul (Korea, Republic of); OECD Nuclear Energy Agency, Paris (France); Uranium Institute, London (United Kingdom); Korean Nuclear Society, Seoul (Korea, Republic of); Korea Atomic Industrial Forum, Seoul (Korea, Republic of); 198 p; 1998; p. 162-163; International symposium on evolutionary water cooled reactors: strategic issues, technologies and economic viability; Seoul (Korea, Republic of); 30 Nov - 4 Dec 1998; IAEA-SM--353-18P; 3 refs, 1 fig
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