Numerical simulation of PHEBUS FPT-3 experiment by using COMPASS code
- 1. Korea Atomic Energy Research Institute (KAERI), Daejeon (Korea, Republic of)
Description
As a part of the integrated severe accident code development project in Korea, KAERI (Korea Atomic Energy Research Institute) has been developing the stand-alone severe accident analysis code, COMPASS (COre Meltdown Progression Accident Simulation Software), which simulate the in-vessel severe accident phenomena including the core heat up, material melting and relocation, corium behavior in lower plenum, vessel failure. For the purpose of COMPASS code validation, the numerical simulation for PHEBUS FPT3 experiment has been conducted. In COMPASS code, the core and surrounding structure in a test section are consisted of two-dimensional node system, and the mass and energy equations are established for the main component in a core and surrounding structures. The temperature evolution of core and surrounding structure at the various location of a test section are pursued and compared with the experimental data as well as the numerical results of MELCOR code. The hydrogen generation rate and the final mass distribution are compared among the experimental data and the numerical results of COMPASS and MELCOR. Generally, COMPASS and MELCOR codes are well predicting the temperature evolution and hydrogen generation rate in the experimental. And, COMPASS are predicting a little bit smaller mass relocation compared with experimental data, while MELCOR has a larger mass relocation. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th Japan-Korea symposium on nuclear thermal hydraulics and safety (NTHAS10)
- Imprint Pagination
- 592 p.
- Journal Page Range
- 6 p.
Conference
- Title
- 10. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS10
- Dates
- 27-30 Nov 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48059608
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOUNDARY CONDITIONS; CLADDING; COMPUTER CODES; CONTROL ELEMENTS; FISSION PRODUCTS; FUEL ELEMENT CLUSTERS; INTERSTITIAL HYDROGEN GENERATION; KAERI; MELTDOWN; REACTOR ACCIDENT SIMULATION; REACTOR CORE DISRUPTION; REACTOR VESSELS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DEPOSITION; FUEL ASSEMBLIES; ISOTOPES; KOREAN ORGANIZATIONS; MATERIALS; NATIONAL ORGANIZATIONS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SIMULATION; SURFACE COATING
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Paper ID: NTHAS10_sub_data/pdf/N10P1015.pdf; 9 refs., 11 figs.