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Article

Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam

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Pages 650-660 | Received 18 Jan 2019, Accepted 26 Apr 2019, Published online: 13 May 2019

References

  • Chung HM. Fuel behavior under loss-of-coolant accident situations. Nucl Eng Technol. 2005 Aug;37:327–362.
  • Meyer R. Fuel behavior under abnormal conditions. Washington (DC): The U.S. Nuclear Regulatory Commission; 2014. (Report no. NUREG/KM-0004).
  • Fuketa T, Nagase F. Behavior of fuel with zirconium alloy cladding in reactivity-initiated accident and loss-of-coolant accident. ASTM STP. 2018;1597:52–92.
  • OECD/NEA. Nuclear fuel behaviour in Loss-of-coolant Accident (LOCA) Conditions: state-of-the-art Report. Paris (France): Oganisation for economic co-operation and development nuclear energy agency; 2009.
  • OECD/NEA. Nuclear fuel safety criteria technical review. Second ed. Paris (France): Oganisation for economic co-operation and development nuclear energy agency; 2012.
  • Baker L, Just LC. Studies of metal-water reaction at high temperatures. III. Experimental and theoretical studies of the zirconium-water reaction. Argonne (Illinois): Argonne National Laboratory; 1962. (Report no. ANL-6548).
  • Ballinger RG, Dobson WG, Biederman RR. Oxidation reaction kinetics of Zircaloy-4 in an unlimited steam environment. J Nucl Mater. 1976;62:213–220.
  • Kawasaki S, Furuta T, Suzuki M. Oxidation of Zircaloy-4 under high temperature steam atmosphere and its effect on ductility of cladding. J Nucl Sci Technol. 1978 Aug;15:589–596.
  • Pawel RE, Cathcart JV, McKee RA. The kinetics of oxidation of Zircaloy-4 in steam at high temperatures. Electrochem Soc. 1979 Jul;126:1105–1111.
  • Leistikow S, Schanz G. Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions. Nucl Eng Des. 1987 Aug;103:65–84.
  • Uetsuka H, Hofmann P. High-temperature oxidation kinetics of Zircaloy-4 in oxygen/argon mixtures. J Nucl Mater. 1989;168:47–57.
  • The Nuclear Safety Commission of Japan. Treatment of high burn-up fuels for safety evaluation in reactivity-initiated events of commercial LWR. Japan: The Nuclear Safety Commission of Japan; 1998. in Japanese.
  • Mardon JP, Charquet D, Senevat J. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy. ASTM STP. 2000;1354:505–524.
  • Mutyala M. Westinghouse fuel direction. Proc. 2004 International Meeting on LWR Fuel Performance; 2004 Sep 19–22; Orlando (Florida).
  • Watanabe S, Kido T, Arakawa Y. Performance of M-MDA cladding in the commercial reactor up to 73 GWd/tU. Proc. WRFPM2008; 2008 Oct 19–22; Seoul (Korea).
  • Steinbrück M, Vér N, Große M. Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600–1200°C. Oxid Met. 2011;76:215–232.
  • Chuto T, Nagase F, Fuketa T. High temperature oxidation of Nb-containing Zr alloy cladding in LOCA conditions. Nucl Eng Technol. 2009;41:163–170.
  • Billone M, Yan Y, Burtseva T, et al. Cladding embrittlement during postulated loss-of-coolant accidents. Washington (DC): The U.S. Nuclear Regulatory Commission; 2008. (Report no. NUREG/CR-6967, ANL-07/04).
  • Billone MC, Yan Y, Burtseva TA, et al. Cladding behavior during postulated loss-of-coolant accidents. Washington (DC): The U.S. Nuclear Regulatory Commission; 2016. (Report no. NUREG/CR-7219, ANL-16/09).
  • Vandenberghe V, Brachet JC, Le Saux M, et al. Sensitivity to chemical composition variations and heating/oxidation mode of the breakaway oxidation in M5 cladding steam oxidized at 1000°C (LOCA conditions). Proc. TopFuel2012; 2012 Sep 2–6; Manchester (United Kingdom).
  • Yamato M, Nagase F, Amaya M. Reduction in the onset time of breakaway oxidation on Zircaloy cladding ruptured under simulated LOCA conditions. J Nucl Mater. 2014;445:78–83.
  • Sato D, Kido T, Mazaki Y. In-pile behavior of M-MDA, advanced PWR fuel cladding irradiated up to 73 GWd/t(R) in a commercial reactor. Proc. WRFPM2011; 2011 Sep 11–14; Chengdu (China).
  • Adamson RB, Rudling P. 4 - Properties of zirconium alloys and their applications in light water reactors (LWRs). In: Murty KL, editor. Woodhead Publishing Series in Energy, Materials ageing and degradation in light water reactors. Sawston, Cambridge: Woodhead Publishing; 2013. p. 151–245.
  • Lemaignan C. 2.07 - Zirconium alloys: properties and characteristics. In: Konings RJM, editor. Comprehensive nuclear materials. Amsterdam: Elsevier; 2012. p. 217–232.
  • Uetsuka H. Oxidation of Zircaloy-4 under limited steam supply at 1000 and 1300°C. Karlsruhe (Germany): Institut fur Material- und Festkorperforschung Projekt Nukleare Sicherheit; 1984. (Report no. KfK 3848).
  • Nagase F, Otomo T, Uetsuka H. Oxidation kinetics of low-Sn Zircaloy-4 at the temperature range from 773 to 1,573 K. J Nucl Sci Technol. 2003;40:213–219.
  • Chuto T. Oxidation of high burnup fuel cladding in LOCA conditions. presented at FSRM2010: 2010 May 19–20; Mito (Japan).
  • Ozawa M, Takahashi T, Homma T, et al. Behavior of irradiated Zircaloy-4 fuel cladding under simulated LOCA conditions. ASTM STP. 2000;1354:279–299.
  • Aomi M, Nakatsuka M, Komura S, et al. Behavior of BWR fuel cladding tubes under simulated LOCA conditions. Proc. ICONE-7; 1999 Apr 19–23; Tokyo (Japan).
  • Nagase F, Otomo T, Uetsuka H. Experiments on high burnup fuel behavior under LOCA conditions at JAERI. Proc. 2000 International Topical Meeting on Light Water Reactor Fuel Performance; 2000 Apr 10–13; Park City, Utah (USA).
  • Portier L, Bredel T, Brachet J, et al. Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5 alloys in LOCA conditions. J ASTM Intl. 2005;2:1–24.

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