The effect of hydride morphology on the failure strain of stress-relieved Zircaloy-4 cladding with an outer surface pre-crack under biaxial stress states

References

• U.S. AEC. Regulatory Guide 1.77 - Assumptions used for evaluating a control rod ejection accident for pressurized water reactors. U.S. Atomic Energy Commission - Directorate of Regulatory standards, Regulatory guide 1.77, 1974 May. Washington (DC).
   Google Scholar
• Macdonald PE, Seiffer SL, Martinson ZR, et al. Assessment of light water reactor fuel damage during a reactivity initiated accident. Paper presented at: CSNI specialist meeting on safety aspects of fuel behavior in off-normal and accident conditions; 1980 Sep 1–4; Espoo, Helsinki, Finland.
   Google Scholar
• NEA. Nuclear fuel behaviour under reactivity-initiated accident (RIA) conditions. France: Nuclear Energy Agency, OECD; 2010. (Report NEA No. 6847). ISBN 978-92-64-99113-2.
   Google Scholar
• Desquines J, Koss DA, Motta AT, et al. The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA). J Nucl Mater. 2011;412:250–267.
   Web of Science ®Google Scholar
• Fuketa T, Nagase K, Ishijima K, et al. NSRR/RIA experiments with high-burnup PWR fuels. Nucl Saf. 1996;37(4):328–342.
   Google Scholar
• Fuketa T, Sasajima H, Sugiyama T. Behavior of high-burnup PWR fuels with low-tin zircaloy-4 cladding under reactivity-initiated-accident conditions. Nucl Technol. 2001;133:50–62.
   Web of Science ®Google Scholar
• Udagawa Y, Sugiyama T, Suzuki M, et al. Stress biaxiality in high-burnup PWR fuel cladding under reactivity-initiated accident conditions. J Nucl Sci Technol. 2013;50(6):645–653.
   Web of Science ®Google Scholar
• Fukuda T. Development of pre-cracked cladding specimen for PCMI failure study. Tokai, Japan; 2010 May 19–20. (Fuel Safety Research Meeting 2010).
   Google Scholar
• Mihara T, Udagawa Y, Sugiyama T, et al. The influence of hydride morphology on the crack propagation through fuel cladding wall. Paper presented at: 2014 international congress on advances in nuclear power plants; 2014 Apr 6–9; Charlotte, NC, USA.
   Google Scholar
• Nagase F, Fuketa T. Investigation of hydride rim effect on failure of Zircaloy-4 cladding with tube burst test. J Nucl Sci Technol. 2005;42(1):58–65.
   Web of Science ®Google Scholar
• Menibus AH, Auzoux Q, Mongabur P, et al. Fracture of Zircaloy-4 cladding tubes with or without hydride blisters in uniaxial to plane strain conditions with standard and optimized expansion due to compression tests. Mater Sci Eng A. 2014;604:57–66.
   Web of Science ®Google Scholar
• Leroy M, Parrot A, Leclercq S. Failure characteristics of cladding tubes under RIA conditions through electromagnetic forming, Transactions, SMiRT 19. Toronto, Canada; 2007.
   Google Scholar
• Shinozaki T, Udagawa Y, Mihara T, et al. Improved-EDC tests on the Zircaloy-4 cladding tube with and outer surface pre-crack. J Nucl Sci Technol. 2016;53(9):1426–1434.
   Web of Science ®Google Scholar
• Li F, Mihara T, Udagawa Y, et al. Biaxial-EDC test attempts with pre-cracked Zircaloy-4 cladding tubes. Paper presented at: 25th international conference on nuclear engineering; 2017 May 14–18; Shanghai, China.
   Google Scholar
• Schrire DI, Pearce JH. Scanning electron microscope techniques for studying Zircaloy corrosion and hydriding. In: Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP1245. Philadelphia; 1994. p. 98–115
   Google Scholar
• Udagawa Y, Mihara T, Sugiyama T, et al. Simulation of the fracture behavior of Zircaloy-4 cladding under reactivity-initiated accident conditions with a damage mechanics model combined with fuel performance codes FEMAXI-7 and RANNS. J Nucl Sci Tech. 2014;51(2):208–219.
   Web of Science ®Google Scholar
• Dassault Systemes Simulia Corp. Abaqus 6.11 analysis user’s manual. Providence, RI: Dassault Systemes Simulia Corp.; 2011. (Chapter 23, Progressive Damage and Failure).
   Google Scholar
• Une K, Nogita K, Ishimoto S, et al. Crystallography of zirconium hydrides in recrystallized Zircaloy-2 fuel cladding by electron backscatter diffraction. J Nucl Sci Tech. 2004;41(7):731–740.
   Web of Science ®Google Scholar
• Lanzani L, Ruch M. Comments on the stability of Zirconium hydride phases in Zircaloy. J Nucl Mater. 2004;324:165–176.
   Web of Science ®Google Scholar
• Daum RS, Chu YS, Motta AT. Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction. J Nucl Mater. 2009;392:453–463.
   Web of Science ®Google Scholar
• Barraclough K, Beevers C. Some observations on the deformation characteristics of bulk polycrystalline zirconium hydrides. J Mater Sci. 1969;4:518–525.
   Web of Science ®Google Scholar
• Puls MP. Fracture initiation at hydrides in zirconium. Metall Trans A. 1991;22:2327–2337.
   Web of Science ®Google Scholar
• Simpson LA. Criteria for fracture initiation at hydrides in zirconium-2.5 pct niobium alloy. Metall Trans A. 1981;12:2113–2124.
   Web of Science ®Google Scholar
• Shi SQ, Puls MP. Fracture strength of hydride precipitates in Zr-2.5Nb alloys. J Nucl Mater. 1999;275:312–317.
   Web of Science ®Google Scholar