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Numerical investigation of ballooning and burst for chromium coated zircaloy cladding.

Authors :
Ma, Zehua
Shirvan, Koroush
Wu, Yingwei
Su, G.H.
Source :
Nuclear Engineering & Design. Nov2021, Vol. 383, pN.PAG-N.PAG. 1p.
Publication Year :
2021

Abstract

• Behavior of Cr-coated clad under integral LOCA test is simulated in FEA. • Current burst criteria for Zircaloy is ineffective to capture Cr-coated concept. • New overstress and plasticity instability criteria for the Cr coating are proposed. • Coating thickness is found to be numerically insensitive to burst temperature. Chromium (Cr) coated cladding is one of the most promising accident-tolerant fuels for pressurized water reactors. The behavior of Cr-coated cladding under the accident conditions is crucial to quantify its implication on safety, licensing and economics. This work focuses on the modeling of the burst behavior of Cr-coated cladding under Loss of Coolant Accidents (LOCAs). For this purpose, the material properties and behavior models of Zircaloy and chromium have been studied and implemented into the ABAQUS. Then the ABAQUS models are compared against several burst tests done by Korea Atomic Energy Research Institute (KAERI) and Électricité de France (EDF). During the comparison process, different high temperature creep models, zircaloy cladding burst criteria and coating thicknesses are adopted to investigate the thermo-mechanical performance and burst behavior of Cr-coated claddings under LOCA. Based on the comparative computational analysis, 100% and 85% Cr fracture strength and the strain rate of 0.23 /s and 0.07 /s are proposed as a new overstress burst criterion for coated cladding under a heating rate from 5 K/s and 10 K/s. The effect of coating thickness on the proposed criteria and the ballooning behavior of the coated cladding was predicted to be insignificant. The proposed criteria are beneficial for better understanding of the coated clad burst phenomena and the best estimation of coated clad performance under LOCA scenarios. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
00295493
Volume :
383
Database :
Academic Search Index
Journal :
Nuclear Engineering & Design
Publication Type :
Academic Journal
Accession number :
152977711
Full Text :
https://doi.org/10.1016/j.nucengdes.2021.111420