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Title: Code package {open_quotes}SVECHA{close_quotes}: Modeling of core degradation phenomena at severe accidents

Abstract

The code package SVECHA for the modeling of in-vessel core degradation (CD) phenomena in severe accidents is being developed in the Nuclear Safety Institute, Russian Academy of Science (NSI RAS). The code package presents a detailed mechanistic description of the phenomenology of severe accidents in a reactor core. The modules of the package were developed and validated on separate effect test data. These modules were then successfully implemented in the ICARE2 code and validated against a wide range of integral tests. Validation results have shown good agreement with separate effect tests data and with the integral tests CORA-W1/W2, CORA-13, PHEBUS-B9+.

Authors:
; ;  [1]
  1. Nuclear Safety Institute, Moscow (Russian Federation); and others
Publication Date:
Research Org.:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; American Nuclear Society (ANS), La Grange Park, IL (United States); American Institute of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers (ASME), 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:
115070
Report Number(s):
NUREG/CP-0142-Vol.3; CONF-950904-Vol.3
ON: TI95017079; TRN: 95:022970
Resource Type:
Conference
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; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; WATER COOLED REACTORS; SAFETY ANALYSIS; REACTOR CORE DISRUPTION; MATHEMATICAL MODELS; URANIUM DIOXIDE; DISSOLUTION; FUEL ELEMENTS; OXIDATION; DEFORMATION; CORIUM; MOTION; S CODES; HYDRAULICS; REACTOR SAFETY

Citation Formats

Veshchunov, M S, Kisselev, A E, and Palagin, A V. Code package {open_quotes}SVECHA{close_quotes}: Modeling of core degradation phenomena at severe accidents. United States: N. p., 1995. Web.
Veshchunov, M S, Kisselev, A E, & Palagin, A V. Code package {open_quotes}SVECHA{close_quotes}: Modeling of core degradation phenomena at severe accidents. United States.
Veshchunov, M S, Kisselev, A E, and Palagin, A V. 1995. "Code package {open_quotes}SVECHA{close_quotes}: Modeling of core degradation phenomena at severe accidents". United States. https://www.osti.gov/servlets/purl/115070.
@article{osti_115070,
title = {Code package {open_quotes}SVECHA{close_quotes}: Modeling of core degradation phenomena at severe accidents},
author = {Veshchunov, M S and Kisselev, A E and Palagin, A V},
abstractNote = {The code package SVECHA for the modeling of in-vessel core degradation (CD) phenomena in severe accidents is being developed in the Nuclear Safety Institute, Russian Academy of Science (NSI RAS). The code package presents a detailed mechanistic description of the phenomenology of severe accidents in a reactor core. The modules of the package were developed and validated on separate effect test data. These modules were then successfully implemented in the ICARE2 code and validated against a wide range of integral tests. Validation results have shown good agreement with separate effect tests data and with the integral tests CORA-W1/W2, CORA-13, PHEBUS-B9+.},
doi = {},
url = {https://www.osti.gov/biblio/115070}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 1995},
month = {Fri Sep 01 00:00:00 EDT 1995}
}

Conference:
Other availability
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