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Larsen, H.
Danish Atomic Energy Commission, Risoe. Research Establishment
Danish Atomic Energy Commission, Risoe. Research Establishment
AbstractAbstract
No abstract available
Primary Subject
Source
Jul 1972; 48 p; ISBN 8755001513; 
; 25 refs.
; 25 refs.
Record Type
Report
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AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society international meeting; Washington, D. C; 12 Nov 1972; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(2); p. 593
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AbstractAbstract
No abstract available
Primary Subject
Source
IEEE nuclear science symposium; New York, N. Y; 4 Nov 1970
Record Type
Journal Article
Journal
IEEE (Inst. Elec. Electron. Eng.), Trans. Nucl. Sci; v. NS-18(1); p. 395-402
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AbstractAbstract
No abstract available
Original Title
Wiederholungspruefungen an Druckwasserreaktoren
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 457-460; 1971; ZAED; Leopoldshafen, F.R. Germany; With figs.
Record Type
Book
Literature Type
Conference
Country of publication
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Subramaniam, K.; Saraf, R.K.; Sanyasi Rao, V.V.S.
First national conference on nuclear reactor technology
First national conference on nuclear reactor technology
AbstractAbstract
[en] Full text: Probabilistic safety studies show that human actions contribute significantly to overall safety in nuclear power plants (NPPs). The contribution of potential human errors to risk is quantitatively assessed in a human reliability analysis (HRA) study in terms of human error probabilities (HEPs) and used to arrive at ways to improve human performance. HRA is thus integral to a probabilistic safety assessment (PSA). In order to handle various emergency conditions such as process or support system failure, which can arise in the plant, a set of emergency operating procedures (EOPs) are developed and provided to NPP operators. Operators are trained to diagnose the event that has occurred and then select and carry out the EOP. Human interaction involved in the execution of an EOP plays an important role in determining the course of an event. If errors occur and operators fail to recover from them, the situation can get aggravated and even result in the event turning into an accident. It is therefore essential to carry out a HRA study for EOPs and determine the human interactions that are the dominant contributors to risk. This would enable designers to implement necessary modifications in procedures and/or develop operator aids to support reliable human performance. This paper first discusses the HRA study carried out for the EOP for station blackout (SBO) event in an Indian pressurised heavy water reactor (IPHWR) and then a study for active process water system (APWS) failure event in advanced heavy water reactor (AHWR). Human reliability quantification has been done using accident sequence evaluation programme (ASEP) which is an accident sequence, data driven HRA technique. The HRA covers event detection and diagnosis and post-diagnosis actions involved. The details of human reliability assessment are given in the paper
Primary Subject
Source
Gupta, Satish K. (comp.) (Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)); Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India); 421 p; Nov 2002; p. 308-309; NRT-1: 1. nuclear reactor safety; Mumbai (India); 25-27 Nov 2002
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Book
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Conference
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AbstractAbstract
No abstract available
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Source
4 Dec 1970; 13 p
Record Type
Report
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INIS VolumeINIS Volume
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Kam, F.B.K.; Swanks, J.H.
Oak Ridge National Lab., Tenn. (USA)
Oak Ridge National Lab., Tenn. (USA)
AbstractAbstract
No abstract available
Primary Subject
Source
18 Mar 1971; 31 p
Record Type
Report
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INIS VolumeINIS Volume
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AbstractAbstract
No abstract available
Primary Subject
Source
13 Oct 1970; 2 p
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Report
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AbstractAbstract
No abstract available
Primary Subject
Source
Conference on nuclear power for tomorrow; Atlantic City, NJ; 22 Aug 1972; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(suppl. no. 2); p. 3
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Dampf-Wasser-Separation als Teil des Kuehlkreislaufs. T. 3
Primary Subject
Source
8 refs.; 9 figs.
Record Type
Journal Article
Journal
Konstruktion, Elemente, Methoden; v. 8(11); p. 443-448
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