Uncertainty quantification of fracture boundary of pre-hydrided Zircaloy-4 cladding tube under LOCA conditions
- 1. Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan)
- 2. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)
Description
Highlights: • Fracture boundary uncertainty of pre-hydrided cladding is quantified. • A log-probit model is developed to estimate fracture probability of cladding. • 5% fracture probability with 95% confidence is higher than 15% ECR at 800 wppmH. - Abstract: To quantify the fracture boundary uncertainty for non-irradiated, pre-hydrided Zircaloy-4 cladding tube specimens under loss-of-coolant accident conditions at a light-water reactor, data from integral thermal shock tests obtained by an earlier study are analyzed statistically and the fracture boundary is estimated in terms of probability, as follows. First, a method is proposed to obtain the specimens' fracture probability curve as a function of equivalent cladding reacted (ECR) and initial hydrogen concentration using Bayesian inference with a generalized linear model. A log-probit model is used, modified to reflect the effect of the initial hydrogen concentration on the fracture boundary and the ECR evaluation uncertainty, and scaled to improve convergence. Second, using the modified log-probit model, it is shown that the boundary representing a 5% fracture probability with 95% confidence for the pre-hydrided cladding tube sample is higher than 15% ECR, for initial hydrogen concentrations of up to 800 wppm.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2018.02.037Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2018.02.037;
- PII
- S0029549318302061;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 331
- Journal Page Range
- p. 147-152
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50082136
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CLADDING; CONCENTRATION RATIO; ECOLOGICAL CONCENTRATION; FRACTURES; HYDROGEN; LOSS OF COOLANT; THERMAL SHOCK; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; DIMENSIONLESS NUMBERS; ELEMENTS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NONMETALS; REACTOR ACCIDENTS; REACTORS; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.