Effects of ballooning and rupture on the fracture resistance of Zircaloy-4 fuel cladding tube after LOCA-simulated experiments
Creators
- 1. Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan)
Description
To investigate the relationship between the fracture resistance of a cladding tube and the amount of deformation of the cladding tube due to ballooning and rupture during a loss-of-coolant accident (LOCA), four-point-bending tests were performed using non-irradiated Zircaloy-4 cladding tubes which experienced a LOCA-simulated sequence (ballooning, rupture, high temperature oxidation and quench). According to the obtained results, it was found that the maximum bending stress of the cladding tube after the LOCA-simulated sequence, which was defined as the fracture resistance, correlated to the average thickness of prior-β layer in the cladding tube. Based on the average thickness of prior-β layer, the fracture resistance of the cladding tube with ballooning and rupture was expressed as functions of isothermal oxidation time and temperature and the maximum circumferential strain on the cladding tube.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2018.06.046Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2018.06.046;
- PII
- S0306454918303475;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 120
- Journal Page Range
- p. 798-804
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50079474
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BALLOONING INSTABILITY; CLADDING; FRACTURES; LOSS OF COOLANT; NUCLEAR FUELS; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENERGY SOURCES; FAILURES; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INSTABILITY; IRON ADDITIONS; IRON ALLOYS; MATERIALS; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; REACTOR ACCIDENTS; REACTOR MATERIALS; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.