Published March 2007 | Version v1
Report Open

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 KAERI

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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