Nuclear Engineering and Technology

  • 제52권12호
  • /
  • Pages.2880-2886
  • /
  • 2020
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors

  • Jung, Tae-Sik (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel) ;
  • Na, Yeon-Soo (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel) ;
  • Joo, Min-Jae (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel) ;
  • Lim, Kwang-Young (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel) ;
  • Kim, Yoon-Ho (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel) ;
  • Lee, Seung-Jae (Materials Development Section of Nuclear Fuel Technology Department, KEPCO Nuclear Fuel)
  • 투고 : 2020.01.20
  • 심사 : 2020.05.08
  • 발행 : 2020.12.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

A small leak occurring on the surface of a fuel rod due to damage exposes UO2 to a steam atmosphere. During this time, fission gas trapped inside the fuel rod leaks out, and the gas leakage can be increased due to UO2 oxidation. Numerous studies have focused on the steam oxidation and its thermodynamic calculation in UO2. However, the thermodynamic calculation of the UO2 oxidation in a pressurized water reactor (PWR) environment has not been studied extensively. Moreover, the kinetics of the oxidation of UO2 pellet also has not been investigated. Therefore, in this study, the thermodynamics of UO2 oxidation under steam injection due to a damaged fuel rod in a PWR environment is studied. In addition, the diminishing radius of the UO2 pellet with time in the PWR environment was calculated through an experiment simulating the initial time of steam injection at the puncture.

키워드

과제정보

This study was supported by the Energy Technology Development Program of the Korea Institute of Energy Technology Evaluation and Planning grant funded by the Korean Government, Ministry of Trade, Industry, and Energy (Grant No. 20171510101990).

참고문헌

  1. Z. Hozer, P. Szabo, B. Somfai, M. Cherubini, R. Aldworth, N. Waeckel, T. Delorme, R. Dickson, H. Fujii, J.M. Rey Gayo, W. Grant, A. Gorzel, C. Hellwig, K. Kamimura, T. Sugiyama, J. Klouzal, M. Miklos, F. Nagase, M. Nilsson, M. Petit, S. Richards, S. Lundqvist, M. Stepniewski, K.S. Sim, R. Rehacek, M. Kissane, Leaking Fuel Impacts and Practices, NEA Report, NEA-CSNI-R-2014-10, OECD NEA, 2014.
  2. V. Inozemtsev, Review of Fuel Failures in Water Cooled Reactors, vol. 2, IAEA Nuclear Energy Reports, NF-T, 2010, pp. 1-175. IAEA.
  3. R.J.M. Konings, T. Wiss, O. Benes, Predicting material release during a nuclear reactor accident, Nat. Mater. 14 (2015) 247-252.
  4. J.H. Davies, G.A. Potts, Post-defect behavior of barrier fuel, Proc. Int. Top. Meet. LWR Fuel Perform.Avignon April (1991) 272-284.
  5. D.R. Olander, Oxidation of UO2 by high-pressure steam, Nucl. Technol. 74 (1986) 215-217.
  6. A.R. Massih, UO2 Fuel Oxidation and Fission Gas Release, Quantum Technology Report, TR1vols. 7-004vol. 4, Stral sakerhets myndigheten, 2018.
  7. K. Une, M. Imamura, M. Amaya, Y. Korei, Fuel oxidation and irradiation behaviors of defective BWR fuel rods, J. Nucl. Mater. 223 (1995) 40-50.
  8. K. Lin, C. Chung, J. Yeh, J. Chen, S. Chu, L. Lin, Investigation on the post-defect deterioration of nonbarrier BWR failed rods, Proc. Int. Top. Meet. LWR Fuel Perform. West Palm Beach (1994) 447. April.
  9. J.S. Armijo, Performance of failed BWR fuel, Proc. Int. Top.Meet. LWR Fuel Perform. West Palm Beach (1994) 410. April.
  10. B. Cox, Mechanisms of Hydrogen Absorption by Zirconium Alloys (No. AECL8702), Atomic Energy of Canada Ltd, 1985.
  11. L.E. Thomas, C.E. Beyer, L.A. Chariot, Microstructural analysis of LWR spent fuels at high burnup, J. Nucl. Mater. 188 (1992) 80-89.
  12. D.J. Kim, J.H. Kim, K.S. Kim, J.H. Yang, S.K. Kim, Y.H. Koo, Thermodynamic assessment of UO2 pellet oxidation in mixture atmosphere under spent fuel pool accident, WJNST 5 (2015) 102-106.
  13. P.A. Tempest, P.M. Tucker, J.W. Tyler, Oxidation of UO2 fuel pellets in air at 503 and 543 K studied using X-ray photoelectron spectroscopy and X-ray diffraction, J. Nucl. Mater. 151 (1988) 269-274.
  14. Z. Zhu, The Electrochemical Study of Simulated Spent Nuclear Fuel (SIMFUEL) Corrosion under Permanent Disposal Conditions, The University of Western Ontario, Ph.D. thesis, 2018.
  15. R.J. McEachern, P. Taylor, A review of the oxidation of uranium dioxide at temperatures below 400 ℃, J. Nucl. Mater. 254 (1998) 87-121.
  16. K.K. Bae, B.G. Kim, Y.W. Lee, M.S. Yang, H.S. Park, Oxidation behavior of unirradiated UO2 pellets, J. Nucl. Mater. 209 (1994) 274-279.
  17. J. Abrefah, A. de Aguiar Braid, W. Wang, Y. Khalil, D.R. Olander, High temperature oxidation of UO2 in steam-hydrogen mixtures, J. Nucl. Mater. 208 (1994) 98-110.
  18. K. Hashizume, W.E. Wang, D.R. Olander, Volatilization of urania in steam at elevated temperatures, J. Nucl. Mater. 275 (1999) 277-286.
  19. D.S. Cox, R.F. O'Connor, W.W. Smeltzer, Measurement of oxidation/reduction kinetics to 2100 ℃ using non-contact solid-state electrolytes, Solid State Ionics 53 (1992) 238-254.
  20. J.H. Yang, Y.W. Rhee, K.W. Kang, K.S. Kim, K.W. Song, S.J. Lee, Formation of columnar and equiaxed grains by the reduction of U3O8 pellets to UO2+x, J. Nucl. Mater. 360 (2007) 208-213.
  21. Y.H. Koo, C.H. Shin, S.C. Jeon, D.S. Kim, K.S. Kim, D.J. Kim, J.H. Yang, K.W. Song, D.H. Kook, H.G. Kim, Y.I. Jung, Fission gas release in the micro-cell fuel pellet under normal operating conditions: a simplified approach based on UO2 pellet experience, J. Nucl. Mater. 527 (2019) 151801.
  22. P. Taylor, R.J. Lemire, D.D. Wood, The influence of moisture on air oxidation of UO2: calculations and observations, Nucl. Technol. 104 (1993) 164-170.
  23. P. Taylor, D.D. Wood, D.G. Owen, G.I. Park, Crystallization of U3O8 and hydrated UO3 on UO2 fuel in aerated water near 200 ℃, J. Nucl. Mater. 183 (1991) 105-114.
  24. S. Aronson, Oxidation of UO2 in water containing oxygen, bettis technical review, WAPD-BT-10, October, 1958, p. 93.
  25. K.A. Peakall, J.E. Antill, Oxidation of uranium dioxide in air at 350-1000℃, J. Nucl. Mater. 2 (1960) 194-195.
  26. Y.S. Kim, A thermodynamic evaluation of the U-O system from UO2 to U3O8, J. Nucl. Mater. 279 (2000) 173-180.
  27. R.J. Ackermann, A.T. Chang, C.A. Sorrell, Thermal expansion and phase transformations of the U3O8-z phase in air, J. Inorg. Nucl. Chem. 39 (1977) 75.
  28. D.R. Olander, W.E. Wang, Y.S. Kim, C.Y. Li, S. Lim, S.K. Yagnik, Chemical process in defective LWR fuel rods, J. Nucl. Mater. 248 (1997) 214-219.
  29. P.M. Tucker, The effect of oxygen partial pressure on the kinetics of unirradiated UO2 oxidation, Proc. Workshop Chem.React. Oxide Fuel Fission Prod. Release (1987) 49.

피인용 문헌

  1. Analysis of inconel 600 oxidized under loss-of-coolant accident conditions: A multi-modal approach vol.195, 2022, https://doi.org/10.1016/j.corsci.2021.109950