Published June 1993
| Version v1
Report
Analysis of the FR-2 in-pile accident by the FRAP-T6 code
Description
The analysis of the FR-2 in-pile Loss of Coolant Accident was carried out using FRAP-T6 code. The clad temperature was introduced as that of the coolant with a very high heat transfer coefficient. The clad temperature, the fuel temperature at the center of the rod, the internal pressure variation, stress and strain distribution and the rupture time were calculated and compared to the measured values. Sensitivity studies were carried out and were found to improve the agreement between the calculated and the experimental results. (author). 15 refs, 11 figs, 3 tabs
Additional details
Publishing Information
- Imprint Title
- Behaviour of core materials and fission product release in accident conditions in LWRs
- Imprint Pagination
- 259 p.
- Journal Page Range
- p. 44-52.
- Report number
- IAEA-TECDOC--706
Conference
- Title
- Technical committee meeting on behaviour of core materials and fission product release in accident conditions in LWRs.
- Dates
- 16-19 Mar 1992.
- Place
- Aix-en-Provence (France).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 24067389
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; F CODES; FR-2 REACTOR; FUEL CANS; FUEL RODS; LOSS OF COOLANT; RUPTURES; SIMULATION; TEMPERATURE DISTRIBUTION; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; FAILURES; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; NATURAL URANIUM REACTORS; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS