Development and assessment of best estimate integrated safety analysis code
Description
Improvement of the integrated safety analysis code MARS3.0 has been carried out and a multi-D safety analysis application system has been established. Iterative matrix solver and parallel processing algorithm have been introduced, and a LINUX version has been generated to enable MARS to run in cluster PCs. MARS variables and sub-routines have been reformed and modularised to simplify code maintenance. Model uncertainty analyses have been performed for THTF, FLECHT, NEPTUN, and LOFT experiments as well as APR1400 plant. Participations in international cooperation research projects such as OECD BEMUSE, SETH, PKL, BFBT, and TMI-2 have been actively pursued as part of code assessment efforts. The assessment, evaluation and experimental data obtained through international cooperation projects have been registered and maintained in the T/H Databank. Multi-D analyses of APR1400 LBLOCA, DVI Break, SLB, and SGTR have been carried out as a part of application efforts in multi-D safety analysis. GUI based 3D input generator has been developed for user convenience. Operation of the MARS Users Group (MUG) was continued and through MUG, the technology has been transferred to 24 organisations. A set of 4 volumes of user manuals has been compiled and the correction reports for the code errors reported during MARS development have been published
Availability note (English)
Available from INIS in electronic form; Also available from KAERIFiles
39034214.pdf
Files
(11.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:b26c5bce7313422b3c5d0e6bfece9cc4
|
11.4 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 314 p.
- Report number
- KAERI/RR--2710/2006
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39034214
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ALGORITHMS; EXPERIMENTAL DATA; M CODES; PWR TYPE REACTORS; SAFETY ANALYSIS
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL LOGIC; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 57 refs, 165 figs, 47 tabs