A sensitivity study of the HTGR PROTEUS benchmark using the VSOP94 code package
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
Among the Generation-IV Reactors, the High Temperature Gas cooled Reactor (HTGR) is attractive due to its high temperature heat source for hydrogen production. This study deals with some calculation results of the PROTUES benchmark problem of which the fuel is a pebble type. The PROTUEUS experiment was planned under the framework of an IAEA Coordinated Research Program (CRP) and started in January 1990. The PROTEUS facility at the Paul Scherrer Institute (PSI) in Switzerland was composed of the low-enriched, fuel pebbles and reached its first criticality around July 1992. The VSOP94 code package is used to simulate the PROTEUS benchmark problem with various mesh sizes, energy groups, and streaming effect corrections of the pebble-bed fuel. The sensitivity analysis of the various calculation options of the VSOP94 code is presented in this study
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- 1466 p.
- Journal Page Range
- p. 141-142
Conference
- Title
- 2004 autumn meeting of the KNS
- Dates
- 28-29 Oct 2004
- Place
- Yongpyong (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36102251
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; HEAT SOURCES; HTGR TYPE REACTORS; P CODES; SENSITIVITY; SENSITIVITY ANALYSIS; V CODES
- Descriptors DEC
- COMPUTER CODES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTORS
Optional Information
- Notes
- 6 refs, 1 fig, 1 tab