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Published May 2008 | Version v1
Miscellaneous

A Generation Risk Assessment for CCWS at UCN 3

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Generation Risk Assessment (GRA) is defined as, ' ... the process of predicting the risk of a generation loss during a future operation by estimating the probability and duration of a plant trip or derate due to equipment degradation or failure.' GRA is to a lost generation (MWh/yr) as Probabilistic Safety Assessment (PSA) is to a core damage frequency. 'Generation Risk' is used as a means of determining where capital improvements or decreased (increased) maintenance is appropriate. Also, GRA will help spare parts inventory control, trip monitor development, etc., and eventually become a basis for Nuclear Asset Management. There are two methods to build a GRA model: 1) To build a GRA model from scratch by considering a plant trip, 2) To convert an existing PSA model to a GRA one. A GRA model for a Component Cooling Water System (CCWS) of UCN 3 was developed by converting the existing PSA results. It is not necessary to model an entire plant before applying a GRA. The GRA for the CCWS of UCN 3 is described in this paper

Part of:
Proceedings of the Korean Nuclear Society Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2008 spring meeting of the KNS
Dates
29-30 May 2008
Place
Kyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
39109244
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
HAZARDS; PROBABILISTIC ESTIMATION; PROBABILITY; SAFETY ANALYSIS; ULCHIN-3 REACTOR
Descriptors DEC
CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 2 figs