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Shvirayev, Y.V.; Morozov, V.B.; Barsukov, A.F.; Tokmachev, G.V.; Derevyankin, A.A.
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors1994
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors1994
AbstractAbstract
[en] In compliance with the current regulatory documents issued by the State Supervisory Authority of the Russian Federation PSAs shall be incorporated in the NPP design process. PSA results shall demonstrate that the estimated values of core damage frequencies and excessive releases do not exceed the set target values of 1.0E-5 and 1.0E-7 per reactor/year, respectively. An excessive release is a release that may require population evacuation from the areas located at certain distances from the site set in the NPP Siting Rules. Thus NPP design shall incorporate level 2 PSA (with some elements of the third level) that shall define a complete variety of possible NPP radiation incidents (when the set excessive release values are exceeded) and evaluate their frequencies of occurrence, amounts and consequences (dose commitments). Consequently, a PSA is an integral part of a NPP design required for licensing. Moreover, presently PSAs along with deterministic analyses have become the main tool for decision-making in the field of safety improvement of the NPPs operating and being designed. 5 refs, 2 tabs
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International Atomic Energy Agency, Vienna (Austria); 264 p; ISSN 1011-4289;
; Mar 1994; p. 72-80; Technical committee meeting on advances in reliability analysis and probabilistic safety assessment for nuclear power reactors; Budapest (Hungary); 7-11 Sep 1992

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