Published October 1981
| Version v1
Report
Open
Estimation of fuel temperature increase during coolant boiloff accident
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
Fuel rod temperature increase during coolant boiloff accident due to unavailable ECCS was analyzed using a simple time dependent model. A standard case was first selected and its results clarified how is the fuel temperature behavior during the boiloff accident. Then the sensitivity studies for various parameters were performed to know what parameters have important roles. As a result of analyses, it was shown that the coolant mixture level in the core has a dominant effect on the core heatup and that fuel rod claddings will probably slump or melt before its full oxidation. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
13689205.pdf
Files
(1.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:bb5fa9e20857c62dd36a4fde07779e92
|
1.6 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- JAERI-M--9710
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13689205
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- B CODES; COOLANTS; ECCS; FUEL ELEMENTS; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; LOSS OF COOLANT; REACTOR CORES; SAFETY ANALYSIS; SENSITIVITY; T CODES; TEMPERATURE MEASUREMENT; TIME DEPENDENCE; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; METALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; TRANSITION ELEMENTS