Published October 2010 | Version v1
Miscellaneous

Development of the Phenomenological Uncertainty Analysis Methodology using MELCOR code for the Containment Failure Probability of Level 2 PSA

  • 1. Seoul National University, Seoul (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The severe accident considering nuclear power plants has extremely low occurrence probability. But if the severe accident occurs, hazards influenced to public are very large. So it is necessary that quantitative analysis of the severe accident occurrence probability, phenomenological analysis of the accident progression process, and the prediction of outcomes were necessary. Therefore the severe accident analysis using MELCOR code has been performed around the regulatory body, the Korea institute of nuclear safety (KINS). But the severe accident analysis has been done conservatively, because the severe accident phenomena have large uncertainties

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

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

Conference

Title
2010 autumn meeting of the KNS
Dates
21-22 Oct 2010
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42085226
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTAINMENT; FAILURES; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR ACCIDENTS; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
3 refs, 3 figs, 1 tab