Published June 1996 | Version v1
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Validation of RELAP5/KMRR for HANARO Accident Analyses

  • 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

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MF available from INIS under the Report Number.

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Publishing Information

Imprint Pagination
81 p.
Report number
KAERI/TR--715/96