Analysis of the vent path through the pressurizer manway under the loss of residual heat removal (RHR) system during mid-loop operation in PWR
- Korea Atomic Energy Research Inst., Taejon (Korea, Republic of). Safety Improvement Research Team
The present study is to analyze an integral test, BETHSY 6.9a, which was conducted in the large scale test facility of BETHSY in CEN-Grenoble of CEA, France. It represents the accident where the loss of RHR occurs during mid-loop operation with pressurizer manway open. The main purposes are to gain insights on the physical phenomena anticipated during the accident and to assess prediction capabilities of both CATHARE2 and RELAP5/MOD3.1 for reliable plant analysis. Accordingly, the results of the present analysis would provide fundamental knowledge for the relevant plant application. As results, overall behavior and main phenomena observed in the experiment could be predicted reasonably by both codes, however, the predictions on some parameters were slightly deviated from the experiment. Particularly, both codes in common predicted that the gravity fed could be possible but it would not be sufficient enough to prevent from the fuel rod heatup, as observed in the experiment. Two significant problems, however, have been encountered in the code simulations. One is associated with enormous computing time due to extremely small time step for both codes and the other is concerned with unexpected large mass error caused by RELAP5.
- OSTI ID:
- 251032
- Report Number(s):
- CONF-960306-; ISBN 0-7918-1226-X; TRN: 96:015353
- Resource Relation:
- Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 3: Safety and reliability; Rao, A.S. [ed.] [General Electric Nuclear Engineering, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 595 p.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
PWR TYPE REACTORS
REACTOR SHUTDOWN
RHR SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTOR ACCIDENTS
LOSSES
COMPUTERIZED SIMULATION
C CODES
R CODES
COMPUTER CODES
EVALUATION