会议专题

Assessment of the Wall and Interphase Friction Modules in SPACE Code

The SPACE code is a system code to predict thermal-hydraulic behaviors of pressurize water nuclear reactors. The program for developing this code was launched in 2006, and a demo version is on the edge of release this year. In this code, Korea Atomic Energy Research Institute (KAERI) has been in charge of development of models and correlations: flow regime maps, wall/interfacial frictions, wall/interfacial heat transfer and droplet entrainment and de-entrainment. This paper is dedicated to validate the modules for wall and interfacial frictions. To this end, three basic hydraulic problems were simulated: oscillating manometer, single/two-phase pressure drop test, and ANL vertical test. The simulation results were compared with the experimental data.

SPACE code Wall friction Interfacial friction

B. J. Kim M. K. Hwang K. D. Kim S. W. Lee

Korea Atomic Energy Research Institute Daeduk-daero, Dukjin-dong, Yuseong-gu, Daejon, South Korea

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1787-1801

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)