Published September 1995
| Version v1
Report
VIPRE modeling of VVER-1000 reactor core for DNB analyses
Creators
- 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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27019400
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CODES; DEPARTURE NUCLEATE BOILING; HYDRAULICS; MATHEMATICAL MODELS; NUMERICAL DATA; REACTOR SAFETY; SAFETY ANALYSIS; V CODES; WWER-5 REACTOR
- Descriptors DEC
- BOILING; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-950904--Vol.3.