Published May 1989
| Version v1
Report
Analysis of fuel behaviour under SB-LOCA for Qinshan NPP and some problems encountered in using RELAP5/MOD1, FRAPCON-2 and FRAP-T6 codes
Description
Recently at the Institute of Atomic Energy (IAE), RELAP5/MOD1, FRAPCON-2, and FRAP-T6 have been linked for analyzing the fuel behavior under Small-Break Loss of Coolant Accident (SB-LOCA) conditions for Qinshan Nuclear Power Plant (Qinshan NPP) which is under construction in China. The main results are quite reasonable, but some problems have been found in combining the functions of different codes, for example, when using the initial conditions provided by FRAPCON-2, FRAP-T6 gives incredibly large cladding stress at the beginning of the accident. It is suggested that for these codes some further improvements are desirable. (author). 4 refs, 8 figs, 2 tabs
Additional details
Publishing Information
- Imprint Title
- Water reactor fuel element computer modelling in steady state, transient and accident conditions
- Imprint Pagination
- 322 p.
- Journal Page Range
- p. 234-241.
- Report number
- IWGFPT--32
Conference
- Title
- Technical committee on water reactor fuel element computer modelling in steady state, transient and accident conditions.
- Dates
- 18-22 Sep 1988.
- Place
- Preston (UK).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 21003267
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FUEL CANS; FUEL RODS; HEAT TRANSFER; LOSS OF COOLANT; POWER DISTRIBUTION; QINSHAN REACTOR; STRESS ANALYSIS; TEMPERATURE DISTRIBUTION; TRANSIENTS; VERY HIGH TEMPERATURE
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-TC--659/4.6.