United States Nuclear Regulatory Commission - Protecting People and the Environment

Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR Transient Codes and Updating of MATPRO Package for Modeling of LOCA and RIA Validation Cases with Zr-1%Nb (VVER type) Cladding (NUREG/IA-0209, NSI RRC KI 3067, IRSN-2002/33)

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Publication Information

Date Published: April 2003

Prepared by:
A. Shestopalov, K Lioutov, L. Yegorova
Nuclear Safety Institute of the Russian Research Centre "Kurchatov Institute"
Kurchatov Square 1, Moscow 123182, Russian Federation

Prepared for:
U.S. Nuclear Regulatory Commission, Institute for Radioprotection and Nuclear Safety (France),
and Ministry of Science and Technologies of Russian Federation

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The report presents the results of analytical work on updating and supplementing Zr-1%Nb (E11O) cladding material property models as part of MATPRO package intended for joint use with thermal mechanical codes analyzing high burnup fuel transient behavior. The scope of work also included adapting U.S.NRC's FRAPTRAN code to the behavior analysis of fuel with E110 cladding (VVER type) and carrying out of the code assessment using selected experimental data. Satisfactory compliance of the results calculated by modified FRAPTRAN version with in-pile RIA and out-of-pile LOCA simulated test results is obtained. The obtained calculation data have been also compared with the predictions of the FRAP-T6 (U.S.NRC) and SCANAIR (IRSN, France) codes modified earlier.

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