Horak, W.C.; Reisman, A.; Purvis, E.E. III.
Brookhaven National Lab., Upton, NY (United States). Funding organisation: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)1997
Brookhaven National Lab., Upton, NY (United States). Funding organisation: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)1997
AbstractAbstract
[en] The Soviet Union established a system of specialized regional facilities to dispose of radioactive waste generated by sources other than the nuclear fuel cycle. The system had 16 facilities in Russia, 5 in Ukraine, one in each of the other CIS states, and one in each of the Baltic Republics. These facilities are still being used. The major generators of radioactive waste they process these are research and industrial organizations, medical and agricultural institution and other activities not related to nuclear power. Waste handled by these facilities is mainly beta- and gamma-emitting nuclides with half lives of less than 30 years. The long-lived and alpha-emitting isotopic content is insignificant. Most of the radwaste has low and medium radioactivity levels. The facilities also handle spent radiation sources, which are highly radioactive and contain 95-98 percent of the activity of all the radwaste buried at these facilities
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1997; 8 p; 32. intersociety energy conversion engineering conference; Honolulu, HI (United States); 27 Jul - 2 Aug 1997; CONF-970701--6; CONTRACT AC02-76CH00016; Also available from OSTI as DE97006713; NTIS; US Govt. Printing Office Dep
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[en] The problem addressed is how to improve the performance of engineers in the design, operation, and maintenance of nuclear power plants. The application of computer science to this problem offers a challenge in maximizing the use of developments outside the nuclear industry and setting priorities to address the most fruitful areas first. Areas of potential benefits include data base management through design, analysis, procurement, construction, operation maintenance, cost, schedule and interface control and planning, and quality engineering on specifications, inspection, and training
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Argonne National Lab., IL (USA); p. 205-207; 10 Dec 1984; p. 205-207; Nuclear power high technology colloquium; Williamsburg, VA (USA); 10-12 Dec 1984; Available from NTIS, PC A13/MF A01; 1 as DE86012079
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[en] Optimizing Quality Assurance activities by taking advantage of technological improvements is an issue directly related to overall product cost, quality, and delivery schedules. Use of automated tooling and numerical control have reduced manufacturing cycle time and thereby enabled better response to changing consumer tastes and market demand. Non-nuclear industries are using computer-aided technology for in-process inspection and final product acceptance. Non-destructive examination can also be performed real-time, on the production line. The challenge faced by the nuclear industry is to make the best use of new and emerging technology while satisfying compliance requirements. Currently, use of new methods is hampered by uncertainty about the affect on regulatory issues. Ways of using the technology have been developed for commercial applications without consideration of nuclear requirements
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Argonne National Lab., IL (USA); p. 209-210; 10 Dec 1984; p. 209-210; Nuclear power high technology colloquium; Williamsburg, VA (USA); 10-12 Dec 1984; Available from NTIS, PC A13/MF A01; 1 as DE86012079
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[en] Artificial intelligence (AI) is a high technology field that can be used to provide problem solving diagnosis, guidance and for support resolution of problems. It is not a stand alone discipline, but can also be applied to develop data bases for retention of the expertise that is required for its own knowledge base. This provides a way to retain knowledge that otherwise may be lost. Artificial Intelligence Methodology can provide an automated construction management decision support system, thereby restoring the manager's emphasis to project management
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Argonne National Lab., IL (USA); p. 211-220; 10 Dec 1984; p. 211-220; Nuclear power high technology colloquium; Williamsburg, VA (USA); 10-12 Dec 1984; Available from NTIS, PC A13/MF A01; 1 as DE86012079
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[en] VVERs are Soviet designed PWRs. Each successive design has incorporated additional features to prevent and mitigate the effects of accidents. A number of generic features differ sharply from western units. Although these are standard basic models, there are a number of significant variations between models. Units are operating and are in various stages of completion in Bulgaria, the Czech Republic, Hungary, Slovakia, Russia, and Ukraine. Units are in the process of being constructed in Cuba. Units are shutdown in Armenia, with consideration being given to restart. Safety issues result from design and site/country specific differences. A number of units are nearly completed or are in advanced stages of construction. Some have either been canceled or placed in a state of suspended animation. The paper addresses key safety issues associated with the seven basic models of VVERs on both a generic basis and a site/country specific basis. Unit models are summarized below. VVER-440 model V230--Actions are being formulated in Russia to attempt to upgrade these to comply with IAEA recommendations (specifics and status will be provided) and to enhance operational safety through activities at one of the two plant sites--this work is to benefit all VVERs. VVER-440 Model V213--Site specific plans are in place or are being formulated for upgrades. There are two of these units in Russia, in the Ukraine, and in Slovinia. There are four in the Czech Republic. VVER-440 Model V318--This is the latest model. Two units are under construction in Cuba. Construction has been at a virtual standstill for over three years. Other units are planned in the Russian Far East. VVER-1000 Model V187--This was the prototype. VVER-1000 Model V302--There are two in Russia and two in Ukraine. VVER-1000 Model V320--This is the latest generation. Units are operating in Bulgaria, Ukraine, and Russia. VVER-1000 ATETs--These have all been canceled
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Peterson, P.F. (ed.) (Univ. of California, Berkeley, CA (United States)); 770 p; ISBN 0-7918-0636-7; ; 1993; p. 611; American Society of Mechanical Engineers; New York, NY (United States); 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering; San Francisco, CA (United States); 21-24 Mar 1993; American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017 (United States)
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[en] A survey has been made of the literature from CMEA countries relating to WWER accident analysis. Key institutions and computer codes are identified and a discussion of accident types given. (author)
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International Atomic Energy Agency, Vienna (Austria); Nuclear Energy Agency, 75 - Paris (France); Proceedings series; 505 p; ISBN 92-0-020188-1; ; 1988; v. 1 p. 237-243; IAEA; Vienna (Austria); International symposium on severe accidents in nuclear power plants; Sorrento (Italy); 21-25 Mar 1988; IAEA-SM--296/115
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[en] On March 4, 1977, a strong earthquake occurred at Vrancea, Romania, about 350 km from the Kozloduy plant in Bulgaria. Subsequent to this event, construction of the unit 2 of the Armenia plant was delayed over two years while seismic features were added. On December 7, 1988, another strong earthquake struck northwest Armenia about 90 km north of the Armenia plant. Extensive damage of residential and industrial facilities occurred in the vicinity of the epicenter. The earthquake did not damage the Armenia plant. Following this event, the Soviet government announced that the plant would be shutdown permanently by March 18, 1989, and the station converted to a fossil-fired plant. This paper presents the results of the seismic analyses of the Soviet-designed VVER (Water-cooled, Water moderated Energy Reactor) plants. Also presented is the information concerning seismicity in the regions where VVERs are located and information on seismic design of VVERs. The reference units are the VVER-440 model V230 (similar to the two units of the Armenia plant) and the VVER-1000 model V320 units at Kozloduy in Bulgaria. This document provides an initial basis for understanding the seismicity and seismic response of VVERs under seismic events. 1 ref., 9 figs., 3 tabs
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1989; 7 p; 10. international conference on Structural Mechanics in Reactor Technology (SMIRT); Anaheim, CA (USA); 14-18 Aug 1989; CONTRACT DOE W-31109-ENG-38; Available from NTIS, PC A02/MF A01 - OSTI as DE89012379; US Govt. Printing Office Dep
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