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ICHMT DIGITAL LIBRARY ONLINE

ISSN 961-91393-0-5

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Year 1995

• 1Heat and Mass Transfer in Severe Nuclear Reactor Accidents
Proceedings of International Symposium - 22 -26 May, 1995, Kusadasi, Turkey

708 pages

Volume price - $176.00

VERIFICATION OF MODIFIED VERSION OF SFD INTEGRAL CODE ICARE2 AGAINST C0RA-W2 (ISP-36) EXPERIMENTAL DATA

A. Kisselev
Institute of Nuclear Safety Institute of Russian Academy of Science (NSI RAS), Russia

A. Voltcheck
lnstitut de Protection et de Surete Nucleaire (IPSN), France

V. F. Strizhov
Nuclear Safety Institute, Russian Academy of Sciences, Bolshaya Tul'skaya 52, Moscow 113191, Russia

A . Derugin
Institute of Nuclear Safety Institute of Russian Academy of Science (NSI RAS), Russia

A. Porracchia
lnstitut de Protection et de Surete Nucleaire (IPSN), France

R. Gonzalez
lnstitut de Protection et de Surete Nucleaire (IPSN), France

F. Jacq
lnstitut de Protection et de Surete Nucleaire (IPSN), France

ABSTRACT

ABSTRACT. The development of integral codes for analysis of NPP core severe accidents requires an association of efforts in international co-operation. An example of such co-operation may be the activities connected with improvement and validation of physical models of the ICARE2 code. The ICARE2 code has been developed in IPSN (France) since 1987. The majority of models used in the code was based on simplified approaches, which can be applied only for definite conditions. The improvement of some code modeling aspects was conducted in 1992-1994 in co-operation between NSI RAS and IPSN. Three modules were implemented in the ICARE2 V2 modl code version during this period (models were developed in NSI RAS in the frame of a detailed mechanistic modules package SVECHA): chemical behaviour during UO₂/Zr/H₂O interactions, melt relocation, fuel-cladding deformation. In this report the results of ICARE2 code validation on C0RA-W2 experimental data are presented. It is shown that:
1. For C0RA-W2 test the modified ICARE2 code (version ICARE2 V2 mod2) correctly predicts the temperature behaviour of the bundle on different elevations, dynamics of melt relocation to lower part of the bundle.
2. Further assessment and model development needs the concepts of internal cladding oxidation, fuel rod cladding failure criteria, the model for oxidation of relocated ceramic melts and the process of solidification of relocated materials.