RBMK thermohydraulic safety assessments using RELAP5/MOD3 codes
The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These assessments show that the RELAP5/MOD3 code can predict major phenomena during postulated accidents in the RBMK reactors.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 79081
- Report Number(s):
- PNL--10613; ON: DE95013853
- Country of Publication:
- United States
- Language:
- English
Similar Records
The RELAP5/MOD3 computer code
Plans and status of RELAP5/MOD3
RELAP5/MOD3 Code Manual
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6980462
Plans and status of RELAP5/MOD3
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:7038326
RELAP5/MOD3 Code Manual
Technical Report
·
Tue Dec 31 23:00:00 EST 1991
·
OSTI ID:5559769