Published March 2021 | Version v1
Journal article

Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments

  • 1. University of Tennessee, Department of Nuclear Engineering, 1412 Circle Dr, Knoxville, TN 37916 (United States)
  • 2. Idaho National Laboratory, Computational Mechanics and Materials Department, PO Box 1625, Idaho Falls, ID 83415-3840 (United States)
  • 3. Kairos Power L.L.C., 707 W Tower Ave, Alameda, CA 94501 (United States)

Description

In the first part of this work, we discussed BISON fuel performance code developments for Zircaloy cladding behavior under loss-of-coolant accident (LOCA) conditions and validation to separate-effects experiments. In this paper, we present modeling developments for UO2 fuel behavior during LOCAs and validation to integral experiments. Code developments are related in particular to modeling axial relocation of fuel fragments during cladding ballooning. Code validation is performed against three integral fuel rod LOCA tests from the Halden IFA-650 series, covering fresh and pre-irradiated fuel rods with and without significant axial fuel relocation observed. Calculated results are systematically compared to experimental data of fuel rod inner pressure evolution during the LOCA transients, time to cladding burst and post-test cladding diameter profile. Comparisons in terms of rod pressure evolution and time to burst appear adequate. Also, the ability to reproduce axial relocation of fuel fragments is demonstrated. Calculated cladding diameter profiles are shown to be considerably sensitive to the selection of the burst failure criterion, highlighting the difficulty to accurately evaluate cladding strains at burst during postulated LOCA scenarios with fuel performance codes.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2020.152645

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2020.152645;
PII
S0022311520312538;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
545
Journal Page Range
vp.
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2020 Elsevier B.V. All rights reserved.