Assessment of RELAP5/MOD3.1 for gravity-driven injection experiment in the core makeup tank of the CARR Passive Reactor (CP-1300)
- Korea Advanced Inst. of Science and Technology, Yusung, Taejon (Korea, Republic of). Nuclear Engineering Dept.
- Korea Inst. of Nuclear Safety, Yusung Taejon (Korea, Republic of). Advanced Reactor Dept.
The objective of the present work is to improve the analysis capability of RELAP5/MOD3.1 on the direct contact condensation in the core makeup tank (CMT) of passive high-pressure injection system (PHPIS) in the CARR Passive Reactor (CP-1300). The gravity-driven injection experiment is conducted by using a small scale test facility to identify the parameters having significant effects on the gravity-driven injection and the major condensation modes. It turns out that the larger the water subcooling is, the more initiation of injection is delayed, and the sparger and the natural circulation of the hot water from the steam generator accelerate the gravity-driven injection. The condensation modes are divided into three modes: sonic jet, subsonic jet, and steam cavity. RELAP5/MOD3.1 is chosen to evaluate the cod predictability on the direct contact condensation in the CMT. It is found that the predictions of MOD3.1 are in better agreement with the experimental data than those of MOD3.0. From the nodalization study of the test section, the 1-node model shows better agreement with the experimental data than the multi-node models. RELAP5/MOD3.1 identifies the flow regime of the test section as vertical stratification. However, the flow regime observed in the experiment is the subsonic jet with the bubble having the vertical cone shape. To accurately predict the direct contact condensation in the CMT with RELAP5/MOD3.1, it is essential that a new set of the interfacial heat transfer coefficients and a new flow regime map for direct contact condensation in the CMT be developed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Nuclear Engineering Dept.; Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 392845
- Report Number(s):
- NUREG/IA--0134; ON: TI97000695
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
GRAVITATION
HIGH PRESSURE COOLANT INJECTION
MODIFICATIONS
NATURAL CONVECTION
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
SAFETY ANALYSIS
SENSITIVITY ANALYSIS
TWO-PHASE FLOW
VAPOR CONDENSATION