Published 2012 | Version v1
Journal article

Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data

  • 1. Westinghouse Nuclear Fuel Business Unit, 1000 Westinghouse Drive, Suite 452, Cranberry Township, PA 16066, (United States)
  • 2. INVAP Nuclear Engineering Department, Avenida Comandante Luis Piedrabuena 4950 San Carlos de Bariloche, R8403CPV Rio Negro, (Argentina)

Description

This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical coefficient derived from code predictions in comparison to the fluid temperature measurement is similar to those from previous mixing tests of similar bundle configurations. The predicted steady-state axial void distributions and time-dependent void profiles based on the Lellouche and Zolotar model generally agree well with the test data. The void model tends to predict lower void at the upper elevation under bulk boiling. The void predictions are in closer agreement with the measurements from the power increase, temperature increase, and flow reduction transients than the depressurization transient. Additional model sensitivity studies showed no significant improvement in the code predictions as compared to the published test data.

Additional details

Publishing Information

Journal Title
Science and Technology of Nuclear Installations (Online)
Journal Volume
2012
Journal Issue
2012
Journal Page Range
p. 11
ISSN
1687-6083