An Analysis of Medium Loss of Coolant Sequence for the Severe Accident Analysis DB
Description
This report contains analysis methodologies and calculation results of medium loss of Coolant sequences for the severe accident analysis database system. The Korean standard nuclear power plant has been selected as a reference plant. Based on the probabilistic safety analysis of the corresponding plant, 10 accident scenarios, which was predicted to have more than 10-10 /ry occurrence frequency, have been analyzed as base cases for the medium loss of Coolant sequence database. The functions of the severe accident analysis database system will be to make a diagnosis of the accident by some input information from the plant symptoms, to search a corresponding scenario, and finally to provide the user phenomenological information based on the pre-analyzed results. The MAAP 4.06 calculation results in this report will be utilized as input data of the severe accident analysis database system
Availability note (English)
Available from INIS in electronic form; Also available from KAERI
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 53 p.
- Report number
- KAERI/TR--3502/2007
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39082581
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTER CALCULATIONS; DATA BASE MANAGEMENT; LOSS OF COOLANT; M CODES; PROBABILITY; REACTOR ACCIDENTS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; MANAGEMENT; REACTOR ACCIDENTS
Optional Information
- Notes
- 3 refs, 151 figs, 8 tabs