Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1996.11a
- /
- Pages.403-408
- /
- 1996
Study on Characteristics of Subchannel Analysis Code at Low Flow Steam Line Break Condition
- Kwon, Hyuk-Sung (Korea Atomic Energy Research Institute) ;
- Lim, Jong-Seon (Korea Atomic Energy Research Institute) ;
- Hwang, Dae-Hyun (Korea Atomic Energy Research Institute) ;
- Chun, Tae-Hyun (Korea Atomic Energy Research Institute) ;
- Park, Jong-Ryul (Korea Atomic Energy Research Institute)
- Published : 1996.11.01
Abstract
The subchannel analysis was performed to verify the behavior of hot channel characteristics and obtain the information to support the core thermal-hydraulic behavior at post-trip steam line break with low flow condition. During this postulated accident, buoyancy-induced cross flow occurs, and the coupled nuclear and thermal-hydraulic interactions become important. The code predictions with TORC are in good agreement with the test data. Under such conditions, the mass flow increase in the hot channel by buoyancy-induced cross flow depends on the parameter
Keywords