Published 2004
| Version v1
Miscellaneous
Progress of accident analysis codes development for gas-cooled reactors
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
- 3. Seoul National University, Seoul (Korea, Republic of)
Description
In an effort to establish a best-estimate accident analysis system for Gas-Cooled Reactors (GCR), two codes are being developed at Korea Atomic Energy Research Institute (KAERI). The MARS-GCR code is for the multi-dimensional system thermal-hydraulic (TH) analysis and the GAMMA code is for the multidimensional and multi-component mixture TH analysis of air-ingress events. This paper describes the developmental progress of both codes
Additional details
Publishing Information
- Imprint Title
- BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings
- Imprint Pagination
- 376 p.
- Journal Page Range
- p. 137-144
Conference
- Title
- International meeting on updates in best estimate methods in nuclear installation safety analysis
- Acronym
- BE-2004
- Dates
- 14-18 Nov 2004
- Place
- Washington, DC (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36058524
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CODES; GCR TYPE REACTORS; REACTOR ACCIDENTS; RISK ASSESSMENT; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HYDRAULICS; MECHANICS; REACTORS
Optional Information
- Notes
- 25 refs, 10 figs, 1 tab