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U.S. Department of Energy
Office of Scientific and Technical Information

Validation experiments and code development for passive safety systems of CP-1300

Conference ·
OSTI ID:23142195
; ; ;  [1];  [2]
  1. Dept. of Nuclear Eng., KAIST 371-1 Ku-song Dong, Yu-sung Gu, Taejon 305-701 (Korea, Republic of)
  2. Accident Analysis Group, KOPEC, 150 Duckjin-dong, Yusong-gu, Taejon 305-353 (Korea, Republic of)
The CARR is developing a large passive pressurized water reactor concept, CP-1300, adopting a passive engineered-safety-feature-system. To confirm the proper functioning of the passive safety system, validation experiments are performed. Through the validation experiments, the physical models about the phenomena which are not well-known have been developed. These models include the direct contact condensation in the CMT, and the film condensation heat transfer in the tube of the PSCS and the PCCS. To simulate the accident of the CP-1300 by using the code, RELAP5/CP has been developed based on RELAP5/MOD3 and the physical models developed from validation experiments. The RELAP5/CP better predicts the experimental data, such as the injection flow rate and the water level of the CMT than the original RELAP5/MOD3.1 does. The new annular turbulent film condensation model is developed based on the KAIST experimental results and adapted in the RELAP5/CP. The simulation results of the PSCS experiment by the RELAP5/CP are in better agreement with the experimental data than those by the original one. The RELAP5/CP, which includes the non-iterative model for wall film condensation, shows good agreement with the experimental heat transfer coefficient of steam condensation in a vertical tube of PCCS.
Research Organization:
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
23142195
Country of Publication:
United States
Language:
English