Updated core power curves for ROSA-III facility
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
New core electric power vs. time curves are developed for experiments on boiling-water-reactor (BWR) loss-of-coolant accidents (LOCAs) with the ROSA-III facility. These power curves are determined so that correct rod surface heat flux is obtained on the ROSA-III electric heater rods which represent the BWR nuclear fuel rods. The power curve formerly used in the ROSA-III experiments was determined conservatively so that the rod surface heat flux was higher than that on the BWR fuel rods. The new power curves are determined based on simplified core heat transfer calculations which account for the non-steady heat conduction within the fuel/heater rods. It is assumed that nucleate boiling is maintained on the rod surface throughout the blowdown. Two power curves are presented with which correct heat flux is obtained on the ROSA-III average-power and peak-power rods, respectively. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
16046322.pdf
Files
(1.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 56 p.
- Report number
- JAERI-M--84-029
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 16046322
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FUEL CANS; FUEL RODS; HEAT FLUX; HEAT TRANSFER; HEATERS; HEATING; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS; SENSITIVITY; SIMULATION; TEMPERATURE DEPENDENCE; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS