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
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