Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics

Citation
M. Kuroda et al., Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics, NUCL ENG DE, 203(2-3), 2001, pp. 185-194
Citations number
29
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR ENGINEERING AND DESIGN
ISSN journal
00295493 → ACNP
Volume
203
Issue
2-3
Year of publication
2001
Pages
185 - 194
Database
ISI
SICI code
0029-5493(200101)203:2-3<185:AOTFBO>2.0.ZU;2-T
Abstract
In order to elucidate the fracture behavior of light water reactor (LWR) fu el rods under reactivity initiated accident (RIA) conditions, an analysis b ased on fracture mechanics has been performed for several types of hydrided cladding tubes Fracture mechanics parameters such as stress intensity fact or (SIF), J-integral and plastic yield load were estimated by finite elemen t method (FEM) analysis, and the failure assessment diagram (FAD) was const ructed using the fracture mechanics parameters to estimate the failure stre ss of the claddings. It was found from the FAD that the predicted fracture stress of the claddings was qualitatively consistent with the experimental results obtained by pulse irradiation tests in the Nuclear Safety Research Reactor (NSRR) and high-pressurization-rate burst tests at Japan Atomic Ene rgy Research Institute (JAERI). (C) 2001 Elsevier Science B.V. All rights r eserved.