ITEMS

modern scholarly publishers in the finest tradition

	Search

Annals of the Assembly for International Heat Transfer Conference 13

ISBN 1-56700-225-0 / CD 1-56700-226-9

Volumes per year:

various

Year 2006

DOI: 10.1615/IHTC13.p7

TRANSIENT SIMULATION OF NUCLEAR REACTOR SAFETY BASED ON A NEW CHOKED FLOW MODEL

M. S. Chung
Korea Institute of Energy Research, Daejeon, Republic of Korea

J. W. Kim
Korea Institute of Energy Research, Daejeon, Republic of Korea

ABSTRACT

Thermal hydraulic system transient is calculated using a new choked flow model which is based on the sound speed of two-phase flow. The choked flow model is derived analytically from the characteristic analysis of a hyperbolic two-fluid model. The two-fluid equations including the surface tension effect in the momentum equations have real eigenvalues representing the sound wave propagation speeds in the non-equilibrium two-phase flow. In the present study, the choked flow model is implemented into a system analysis code RELAP5/MOD3. Following to the Marviken LBLOCA test compared with experimental data, the SBLOCA tests of the Typical PWR during the normal operation of nuclear power plants are performed. Also, the calculated results using the present model and the earlier Trapp-Ransom models are compared with each other. The assessment results adopting the present model without any adjustment like an empirical discharge coefficient are reasonable and compatible in the choked flow calculations compared with those using the earlier choked flow models.