Published September 1995 | Version v1
Report

VIPRE modeling of VVER-1000 reactor core for DNB analyses

  • 1. Westinghouse Electric Corporation, Pittsburgh, PA (United States)
  • 2. Nuclear Research Institute, Prague, (Czech Republic)

Description

Based on the one-pass modeling approach, the hot channels and the VVER-1000 reactor core can be modeled in 30 channels for DNB analyses using the VIPRE-01/MOD02 (VIPRE) code (VIPRE is owned by Electric Power Research Institute, Palo Alto, California). The VIPRE one-pass model does not compromise any accuracy in the hot channel local fluid conditions. Extensive qualifications include sensitivity studies of radial noding and crossflow parameters and comparisons with the results from THINC and CALOPEA subchannel codes. The qualifications confirm that the VIPRE code with the Westinghouse modeling method provides good computational performance and accuracy for VVER-1000 DNB analyses

Additional details

Publishing Information

Imprint Title
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Volume 3, Sessions 12-16
Imprint Pagination
1001 p.
Journal Page Range
p. 2112-2118.
Report number
NUREG/CP--0142-Vol.3

Conference

Title
7. international meeting on nuclear reactor thermal hydraulics.
Dates
10-15 Sep 1995.
Place
Saratoga, NY (United States).

Optional Information

Secondary number(s)
CONF-950904--Vol.3.