Investigation on Halden LWR ramp test by means of FEMAXI-III code (PWR version)
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Some investigation on LWR ramp tests in high pressure loop at HBWR was carried out with PWR version FEMAXI-III code. The verification of FEMAXI-III PWR version was conducted by means of irradiation data of LWR ramp test at HBWR. Calculated results agreed well with the inpile data on creepdown, fuel diameter change and ridge height, except for those on fission gas release. Therefore, the validity of the application of FEMAXI-III PWR version to analyse the LWR ramp test in high pressure loop at HBWR was confirmed. The effects of pellet shape and burnup on fuel behavior during ramp test were also clarified. The effects of irradiation conditions at different type of reactors were investigated by means of FEMAXI-III PWR version. It is revealed that ramp tests at commercial PWR conditions and HBWR conditions result in higher fuel center temperature and higher cladding hoop stress than that in the high pressure loop at HBWR. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
22069529.pdf
Files
(1.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:00c03b2f32b2ee53f8e87c9a5cfd6fbe
|
1.4 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- JAERI-M--91-027
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22069529
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BURNUP; CREEP; F CODES; FISSION PRODUCT RELEASE; FUEL CANS; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; HBWR REACTOR; IRRADIATION; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; BHWR TYPE REACTORS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS