Published 1993 | Version v1
Report Open

Probabilistic approach to requalification of existing NPPs under aircraft crash loading

  • 1. St. Petersburg Research and Design Institute Atomenergoproject, St. Petersburg (Russian Federation)

Description

A probabilistic approach to the analysis of NPP safety under aircraft impact is discussed. It may be used both for requalification of existing NPPs and in the process of NPP design. NPP is considered as a system of components: structures, pipes, different kinds of equipment, soil, foundation. The exceeding of the limit probability of the radioactive products release out of containment (i.e. of the NPP safety requirements non-fulfilment) is taken as a system failure criterion. An example of an event tree representing the consequence of events causing the failure is given. Described are the methods of estimate of elementary events probabilities through which a composite probability of the failure is evaluated. (author)

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Part of:
Upgrading of existing NPPs with 440 and 1000 MW WWER type pressurized water reactors for severe external loading conditions. Proceedings. Working material. V. 1, 2

Additional details

Publishing Information

Imprint Title
Upgrading of existing NPPs with 440 and 1000 MW WWER type pressurized water reactors for severe external loading conditions. Proceedings. Working material. V. 1, 2
Imprint Pagination
778 p.
Journal Page Range
p. 325-334
Report number
INIS-XA--184

Conference

Title
SMIRT-12 conference seminar no. 16 on upgrading of existing NPPs with 440 and 1000 MW VVER type pressurized water reactors for severe external loading conditions
Dates
23-25 Aug 1993
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
30053280
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; AIRCRAFT; BUILDINGS; EQUIPMENT; FAILURES; FOUNDATIONS; MECHANICAL STRUCTURES; NUCLEAR POWER PLANTS; PIPES; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; SAFETY ANALYSIS
Descriptors DEC
MECHANICAL STRUCTURES; NUCLEAR FACILITIES; POWER PLANTS; SUPPORTS; THERMAL POWER PLANTS

Optional Information

Notes
5 refs, 5 figs