Assessment of RELAP5/MOD3 With the SNUF Test Simulating Hot Leg Break LOCA in the View of Mass and Energy Release Analysis (NUREG/IA-0198)

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Publication Information

Date Published: February 2001

Prepared by:
S. Joon Hong, G. Cherl Park
Seoul National University
San 56-1, Shillim-Dong, Kwanak-Gu
Seoul, 151-742


Y. Seok Bang, C-Y. Yang
Korea Institute of Nuclear Safety
19 Gusung-Ding Yusung-Gu
Taejon, 305-338

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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SNUF experiment on hot leg break large break loss of coolant accident during post-blowdown was analyzed by RELAP5. As same with the procedure of SNUF experiment, normal operation and blowdown phase were simulated in order, and the initial condition was obtained and compared with the experimental initial condition. The analysis of post-blowdown phase showed that the behavior of primary pressure can be properly simulated by RELAP5 when sufficient heat source is modeled. Resultantly, the release from reactor side broken section and steam generator side broken section were properly predicted. The pressure rise in the second step of pressure behavior was partially well predicted, where the pressure increased by the steam generation in core. The release from the steam generator side broken section was predicted to be little except when there exits large pressure difference between primary system and break boundary. Break size did not affect much on the overall behavior to some degree.

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