skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: VIPRE modeling of VVER-1000 reactor core for DNB analyses

Abstract

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.

Authors:
;  [1];  [2]
  1. Westinghouse Electric Corporation, Pittsburgh, PA (United States)
  2. Nuclear Research Institute, Prague, (Czech Republic)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
OSTI Identifier:
115083
Report Number(s):
NUREG/CP-0142-Vol.3; CONF-950904-Vol.3
ON: TI95017079; TRN: 95:022983
Resource Type:
Technical Report
Resource Relation:
Conference: 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Volume 3, Sessions 12-16; Block, R.C.; Feiner, F. [comps.] [American Nuclear Society, La Grange Park, IL (United States)]; PB: 1001 p.
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; WWER-5 REACTOR; SAFETY ANALYSIS; DEPARTURE NUCLEATE BOILING; V CODES; HYDRAULICS; REACTOR SAFETY; MATHEMATICAL MODELS; NUMERICAL DATA; COMPUTER CODES

Citation Formats

Sung, Y., Nguyen, Q., and Cizek, J. VIPRE modeling of VVER-1000 reactor core for DNB analyses. United States: N. p., 1995. Web. doi:10.2172/115083.
Sung, Y., Nguyen, Q., & Cizek, J. VIPRE modeling of VVER-1000 reactor core for DNB analyses. United States. doi:10.2172/115083.
Sung, Y., Nguyen, Q., and Cizek, J. Fri . "VIPRE modeling of VVER-1000 reactor core for DNB analyses". United States. doi:10.2172/115083. https://www.osti.gov/servlets/purl/115083.
@article{osti_115083,
title = {VIPRE modeling of VVER-1000 reactor core for DNB analyses},
author = {Sung, Y. and Nguyen, Q. and Cizek, J.},
abstractNote = {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.},
doi = {10.2172/115083},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {9}
}