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AbstractAbstract
[en] Full text: As previously noted in the discussions concerning the methods used to provide or replace safety systems, most of the safety systems in the Al-Tuwaitha facility were severely damaged during the bombing, and it was considered too dangerous or difficult to repair or replace them. The condition of the site was such that even basic systems such as an electrical supply and containment structures were not available. As a consequence of the severe damage, essentially all of the entire site infrastructure required replacement. (author)
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Source
International Atomic Energy Agency, Decommissioning and Environmental Remediation Section, Vienna (Austria); 136 p; ISBN 978-92-0-142621-5;
; ISSN 1011-4289;
; Dec 2021; p. 57; Also available on-line: https://www.iaea.org/publications/15053/managing-the-decommissioning-and-remediation-of-damaged-nuclear-facilities; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books


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Rickard, A.R.; George, B.V.
Nuclear Power Co. (Whetstone) Ltd. (UK)1977
Nuclear Power Co. (Whetstone) Ltd. (UK)1977
AbstractAbstract
[en] There is provided a nuclear reactor installation comprising a fluid-cooled nuclear heat source, a primary pressure vessel containing the heat source, an outer envelope enclosing the primary pressure vessel and constituting secondary containment means therefor and providing external-missile protection therefor, and a plurality of auxiliary-facility stations disposed outside the outer envelope, wherein the outer envelope comprises a lower wall portion surrounding the primary pressure vessel, an annular portion integral with the lower wall portion and extending outwardly therefrom, and an upper portion integral with the annular portion and extending over the annular portion and over the primary pressure vessel, the annular portion and the primary pressure vessel being formed with sealable vertical penetrations communicating with the respective auxiliary-facility stations and with the primary pressure-vessel interior respectively and there being provided, in the said upper portion, handling means for lifting reactor components vertically through such penetrations and transporting them over the said annular portion and the primary pressure vessel
Primary Subject
Source
15 Nov 1977; 10 p; CA PATENT DOCUMENT 1021074/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
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Reference NumberReference Number
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Fay, H.P.; Peck, W.S.
Gulf Oil Corp., Pittsburgh, Pa. (USA)1975
Gulf Oil Corp., Pittsburgh, Pa. (USA)1975
AbstractAbstract
No abstract available
Primary Subject
Source
4 Mar 1975; 18 p; CA PATENT DOCUMENT 963765; Available from Commissioner of Patents, Ottawa.
Record Type
Patent
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AbstractAbstract
[en] For the first time, this paper presents and compares the experimental, long-term data of former HDR-containment blowdown experiments CONW and COND, tests V21.1 and V43, and the small-break, long-term blowdown experiments RBE and CON, tests T30.4 and T31.6 from Phases 1 and 2 of the HDR Safety Program in the large-scale HDR-Containment in Germany. The four experiments examined and evaluated in this paper cover the following changes in important parameters: (1) break size; (2) type of blowdown (subcooled water, steam); (3) break position with respect to its axial location in the containment; and (4) operation of Engineered Safety Features (ESF), such as internal spray. Results will be compared and conclusions will be drawn for: (1) vertical temperature distributions; (2) transverse temperature distributions; and (3) convective flows and global natural circulations. The review of the data base indicates the existence of large-scale global natural circulations which have the potential--depending on some conditions--to mitigate and homogenize non-uniform H2-concentration distributions
Primary Subject
Secondary Subject
Source
Rao, A.S. (ed.) (General Electric Nuclear Energy, San Jose, CA (United States)); Duffey, R.B. (ed.) (Brookhaven National Lab., Upton, NY (United States)); Elias, D. (ed.) (Commonwealth Edison, Downers Grove, IL (United States)); 564 p; ISBN 0-7918-1226-X;
; 1996; p. 825-841; American Society of Mechanical Engineers; New York, NY (United States); ICONE 4: ASME/JSME international conference on nuclear engineering; New Orleans, LA (United States); 10-13 Mar 1996; American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017 (United States) $250.00 for the 5-volume set

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Book
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Conference; Numerical Data
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AbstractAbstract
[en] During 15 years of containment experiments in the large-scale, close-to-realistic HDR-containment for the German federally-funded HDR Safety Program, Phases 1 through 3, a large data base of DBA LOCA experiments with subcooled liquid and steam blowdowns has been accumulated. In addition several experiments were performed with small break blowdowns. For both types of scenarios, some experiments were used to examine hydrogen mixing and distributions under a variety of different release and containment atmosphere conditions. This paper, as Part 2 of a series of two, presents an overview of the HDR experiment E11.5 thereby supplementing the information provided on previous HDR-DBA-LOCA experiments V21.1 and V43 as well as medium-sized and small-break LOCA-experiments, T30.4 and T31.6, respectively and the information provided in the companion paper on HDR-experiment T31.5. The break position tested for experiment E11.5 was located in the lower-most part of the HDR containment. This experiment concluded the severe-accident-oriented test series E11 and constitutes a bridge to the previous DBA-oriented LOCA-experiments performed with release positions in the middle section (V21.1 and V43) and upper containment region (T31.5). This paper focuses on the transient long-term spatial evolutions of the relevant containment atmosphere conditions, including light gas mixture distribution
Primary Subject
Source
El-Genk, M.S. (ed.) (Univ. of New Mexico, Albuquerque, NM (United States)); AIChE symposium series, Number 310, Volume 92; 385 p; ISBN 0-8169-0705-6;
; 1996; p. 243-252; American Inst. of Chemical Engineers; New York, NY (United States); 31. national heat transfer conference; Houston, TX (United States); 3-6 Aug 1996; ISSN 0065-8812;
; American Institute of Chemical Engineers, 345 East 47 Street, New York, NY 10017 (United States) $80.00


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Book
Literature Type
Conference; Numerical Data
Country of publication
ACCIDENTS, BWR TYPE REACTORS, CONTAINMENT, DATA, ELEMENTS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, INFORMATION, NONMETALS, NUMERICAL DATA, POWER REACTORS, REACTOR ACCIDENTS, REACTOR SAFETY EXPERIMENTS, REACTORS, RESEARCH AND TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
No abstract available
Original Title
Issledovanie izmeneniya urovnya v kondensatorakh-barboterakh AEhS
Primary Subject
Source
Short note. For English translation see the journal Thermal Engineering (UK).
Record Type
Journal Article
Journal
Teploehnergetika; ISSN 0040-3636;
; (no.2); p. 64-66

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Schade, A.R.; Simpson, D.E.
Hanford Engineering Development Lab., Richland, WA (USA)1979
Hanford Engineering Development Lab., Richland, WA (USA)1979
AbstractAbstract
[en] The Project has undertaken design studies of concepts capable of providing added containment safety margins. Since the events, for which these features provide consequence reductions, are beyond the design basis accident classification, the conceptual designs would not be designed as Engineered Safety Features. A final decision has not been made by the Department of Energy as to the disposition of this advice. It is the Project's plan to develop sufficient design details for these features that construction schedules and cost estimates can be formulated. This information supplemented by the continuing analytical and experimental program to assess the adequacy of FFTF containment margins will enable a decision to be made as to additional features to be added to FFTF and their schedule for implementation
Primary Subject
Source
1979; 7 p; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979; CONF-790816--63; Available from NTIS., PC A02/MF A01
Record Type
Report
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Conference
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AbstractAbstract
[en] This reports contains: (1) an evaluation by Gilbert/Commonwealth (G/C) of the NucleDyne passive Containment System (PCS) as that conceptual design is applied to a Westinghouse, two loop, Pressurized Water Reactor; (2) an evaluation by Westinghouse of two questions about the impact of the PCS on the Nuclear Steam Supply System (NSSS), which were posed by G/C and best answered by an NSSS vendor; and (3) replies to both the Gilbert/Commonwealth report and the Westinghoue report by NucleDyne Engineering Corporation
Primary Subject
Source
Apr 1981; 216 p; Available from NTIS., PC A10/MF A01
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Report
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Demireva, E.; Grigorov, D.; Balabanov, E.
Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation1995
Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation1995
AbstractAbstract
[en] A study of the Kozloduy NPP Unit 2 containment improvement has been carried out. The following objectives are identified: to assess confinement tightness (local tests); to improve tightness; to perform the most urgent repair works; to develop global test procedures including leak tightness at nominal and reduced pressure, structural integrity test and venting flaps reliability test. Nine groups of potential leakage paths have been determined. The ventilation system has been found as the major source of expected leakage having 60 penetrations with size above 250 mm. Proposed modifications of the ventilation system include reduction of the number of inflow and suction valves, replacement of some valves with a better quality ones and installation of isolating valves. It is planned to transfer the experience and results of this study to the other WWER-440 units. 1 ref
Primary Subject
Source
442 p; 1995; p. 253-258; Scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP; Kozloduy (Bulgaria); 25-26 Oct 1994
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Miscellaneous
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AbstractAbstract
[en] The behaviour is described of reactor containments in severe accidents in light water reactors as predicted in the NRC's NUREG-1150 study (USNRC 1987)
Primary Subject
Secondary Subject
Source
Wittman, F.H. (ed.) (Swiss Federal Institute of Technology, Lausanne (Switzerland). Laboratory for Building Materials); 207 p; ISBN 90 6191 738 7;
; 1987; p. 107-117; Balkema; Rotterdam (Netherlands); 9. International conference on structural mechanics in reactor technology (SMIRT 9); Lausanne (Switzerland); 17-21 Aug 1987; 8 refs.; 3 figs.

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