VIPRE modeling of VVER-1000 reactor core for DNB analyses

Technical Report · Fri Sep 01 00:00:00 EDT 1995

DOI:https://doi.org/10.2172/115083· OSTI ID:115083

Sung, Y.; Nguyen, Q. ^[1]; Cizek, J. ^[2]

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

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.

• Research Organization: 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 ID: 115083
• Report Number(s): NUREG/CP--0142-Vol.3; CONF-950904--Vol.3; ON: TI95017079
• Country of Publication: United States
• Language: English

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