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Published May 2008 | Version v1
Miscellaneous

Regulatory PSA Model Development for Risk Evaluation of Kori Nuclear Unit 1 Continued Operation

  • 1. ENESYS Co., Daejeon (Korea, Republic of)
  • 2. KINS, Daejeon (Korea, Republic of)

Description

This purpose of this study is to develop regulatory PSA(Probabilistic Safety Analysis) model for independent risk evaluation of Kori Nuclear Unit 1 continued operation from regulatory perspectives and to quantify CDF(Core Damage Frequency) within Level 1 PSA scope and to gain regulatory insight through this study

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
39109203
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
EVALUATION; HAZARDS; KORI-1 REACTOR; PROBABILITY; REACTOR OPERATION; REGULATIONS; SAFETY ANALYSIS
Descriptors DEC
ENRICHED URANIUM REACTORS; LAWS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 3 figs