Modification of IPSN's SCANAIR Fuel Rod Transient Code for High Burnup VVER Fuel (NUREG/IA-0165, RRC KI 2181, IPSN 99/09)

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Publication Information

Date Published: May 1999

Prepared by:
K. Mikitiouk, INR–RRC
A. Shestopalov, K. Lioutov, L. Yegorova, G. Abyshov, NSI–RRC

Institute of Nuclear Reactors of Russian Research Center "Kurchatov Institute"
Nuclear Safety Institute of Russian Research Center "Kurchatov Institute"
Kurchatov Square 1
Moscow 12382
Russia

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

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The IPSN's transient fuel rod code, SCANAIR, has been modified to analyze pulse tests with high-burnup VVER fuel rods in the Impulse Graphite Reactor (IGR). New and modified models of separate phenomena have been developed, including models for gas plenum temperature, heat transfer from the cladding to the stagnant coolant, the effect of the cladding strain rate on the yield stress, and interruption of the cladding mechanical calculation. Thermal and mechanical properties for the VVER's fuel and Zr-1%Nb cladding were added to the SCANAIR data base on material properties. Changes in the input data file are described, and a sample calculation is presented with the modified code. A FORTRAN listing for the new and modified models is given in an Appendix A.