Validation of RELAP5/KMRR for HANARO Accident Analyses
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
To carry out the accident analyses for the HANARO, RELAP5/MOD2 was modified. The heat transfer correlations and other thermal hydraulic models to account for the finned fuel elements and plate-type heat exchangers were modified to give RELAP5/KMRR, simulation of single pin heat transfer experiments and plate-type heat exchanger was made and compared with experimental results and manufacturer's data. The natural convection experiment using scaled bundle was also simulated to evaluate the code function. The original RELAP5/MOD2 calculation results for the case of loss of electric power and pump seizure were compared with current code results. In the simulation of single pin experiment and heat exchanger model calculation, the code predicts the experimental values well or at least conservatively. The natural convection flow was underpredicted. This is acceptable because thermal hydraulically, it is in the conservative side. The RELAP5/MOD2 and the modified version show almost identical trend. Since the RELAP5/KMRR comprised the unique characteristics of HANARO and it predicted thermal hydraulic behavior in the same manner, we judged that the code could be used for the accident analyses of the HANARO. 6 tabs., 19 figs., 11 refs. (Author) .new
Availability note (English)
MF available from INIS under the Report Number.Files
27063162.pdf
Files
(1.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 81 p.
- Report number
- KAERI/TR--715/96
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 27063162
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CODES; FUEL ASSEMBLIES; HYDRAULICS; KMR REACTOR; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS TESTING REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS