Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Circumferential steady-state creep test and analysis of Zircaloy-4 fuel cladding

  • Choi, Gyeong-Ha (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Shin, Chang-Hwan (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jae Yong (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Byoung Jae (Department of Mechanical Engineering, Chungnam National University)
  • Received : 2020.09.01
  • Accepted : 2021.01.11
  • Published : 2021.07.25
Download PDF
⟨ Previous Next ⟩

Abstract

In recent studies, the creep rate of Zircaloy-4, one of the basic property parameters of the nuclear fuel code, has been commonly used with the axial creep model proposed by Rosinger et al. However, in order to calculate the circumferential deformation of the fuel cladding, there is a limitation that a difference occurs depending on the anisotropic coefficients used in deriving the circumferential creep equation by using the axial creep equation. Therefore, in this study, the existing axial creep law and the derived circumferential creep results were analyzed through a circumferential creep test by the internal pressurization method in the isothermal conditions. The circumferential creep deformation was measured through the optical image analysis method, and the results of the experiment were investigated through constructed IDECA (In-situ DEformation Calculation Algorithm based on creep) code. First, preliminary tests were performed in the isotropic β-phase. Subsequently in the anisotropic α-phase, the correlations obtained from a series of circumferential creep tests were compared with the axial creep equation, and optimized anisotropic coefficients were proposed based on the performed circumferential creep results. Finally, the IDECA prediction results using optimized anisotropic coefficients based on creep tests were validated through tube burst tests in transient conditions.

Keywords

Acknowledgement

This work has been carried out under the Nuclear R&D Program supported by the Ministry of Science and ICT. (NRF-2017M2A8A5015064).

References

  1. H. Rosinger, P. Bera, W. Clendening, Steady-state creep of Zircaloy-4 fuel cladding from 940 to 1873 K, J. Nucl. Mater. 82 (2) (1979) 286-297. https://doi.org/10.1016/0022-3115(79)90011-4
  2. A. Donaldson, R. Horwood, T. Healey, Biaxial Creep Deformation of Zircaloy-4 in the High Alpha Phase Temperature Range, 1983.
  3. D. Kaddour, S. Frechinet, A.-F. Gourgues, J.-C. Brachet, L. Portier, A. Pineau, Experimental determination of creep properties of zirconium alloys together with phase transformation, Scripta Mater. 51 (6) (2004) 515-519. https://doi.org/10.1016/j.scriptamat.2004.05.046
  4. C. Lemaignan, 2.07-Zirconium Alloys: Properties and Characteristics, Comprehensive Nuclear Materials, Elsevier Oxford2012, pp. 217-232.
  5. C. Allison, G. Berna, R. Chambers, E. Coryell, K. Davis, D. Hagrman, D. Hagrman, N. Hampton, J. Hohorst, R. Mason, SCDAP/RELAP5/MOD3. 1 Code Manual, Volume IV: MATPRO-A Library of Materials Properties for Light-Water-Reactor Accident Analysis, DT Hagrman, NUREG/CR-6150, 1993, pp. 4-234. EGG-2720 4.
  6. C. Hunt, Anisotopic Theory and the Measurement and Use of the Anisotropic Factors for Zircaloy-4 Fuel Sheaths, 1975.
  7. H. Rosinger, J. Bowden, R. Shewfelt, The Anisotropic Creep Behaviour of Zircaloy-4 Fuel Cladding at 1073 K, Atomic Energy of Canada Ltd., 1982.
  8. H.-J. Neitzel, H. Rossinger, The Development of a Burst Criterion for Zircaloy Fuel Cladding under LOCA Conditions, Atomic Energy of Canada Ltd., 1980.
  9. A. Committee, Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding, ASTM international, 2013. ASTM B 811-2013.
  10. A.K. Yadav, C.H. Shin, S.U. Lee, H.C. Kim, Experimental and numerical investigation on thermo-mechanical behavior of fuel rod under simulated LOCA conditions, Nucl. Eng. Des. 337 (2018) 51-65. https://doi.org/10.1016/j.nucengdes.2018.06.023
  11. A.K. Yadav, C.-H. Shin, C. Lee, S.-U. Lee, H.C. Kim, Numerical modeling of fuel rod transient response under out of pile test conditions, Prog. Nucl. Energy 113 (2019) 62-73. https://doi.org/10.1016/j.pnucene.2019.01.014
  12. S. Suman, Burst criterion for Indian PHWR fuel cladding under simulated lossof-coolant accident, Nucl. Eng. Technol. 51 (6) (2019) 1525-1531. https://doi.org/10.1016/j.net.2019.04.004
  13. M.K. Khan, M. Pathak, A.K. Deo, R. Singh, Burst criterion for zircaloy-4 fuel cladding in an inert environment, Nucl. Eng. Des. 265 (2013) 886-894. https://doi.org/10.1016/j.nucengdes.2013.08.071
  14. M. MATLAB, MATLAB 2019a, The MathWorks: Natick, MA, USA, 2019.
  15. G.-H. Choi, D.-H. Kim, C.-H. Shin, J.Y. Kim, B.J. Kim, In-situ deformation measurement of Zircaloy-4 cladding tube under various transient heating conditions using optical image analysis, Nucl. Eng. Des. 370 (2020), 110859. https://doi.org/10.1016/j.nucengdes.2020.110859
  16. R. Hill, A theory of the yielding and plastic flow of anisotropic metals, Proc. Roy. Soc. Lond. Math. Phys. Sci. 193 (1033) (1948) 281-297.
  17. K. Pettersson, Nuclear Fuel Behaviour in Loss-Of-Coolant (LOCA) Conditions, Issy-Les-Moulineaux, OECD Nuclear Energy Agency, France, 2009.
  18. H. Rosinger, A model to predict the failure of Zircaloy-4 fuel sheathing during postulated LOCA conditions, J. Nucl. Mater. 120 (1) (1984) 41-54. https://doi.org/10.1016/0022-3115(84)90169-7
  19. K. Geelhood, W. Luscher, J. Cuta, I. Porter, PNNL-19400, FRAPTRAN-2.0: a Computer Code for the Transient Analysis of Oxide Fuel Rods, 1 Rev2, Pacific Northwest National Laboratory, 2016.
  20. D. Powers, R. Meyer, Cladding Swelling and Rupture Models for LOCA Analysis, NUREG-0630, S, Nuclear Regulatory Commission, 1980.
  21. H. Chung, T. Kassner, Deformation Characteristics of Zircaloy Cladding in Vacuum and Steam under Transient-Heating Conditions: Summary Report, Argonne National Lab., 1978.
  22. D. Campello, N. Tardif, M. Moula, M.-C. Baietto, M. Coret, J. Desquines, Identification of the steady-state creep behavior of Zircaloy-4 claddings under simulated Loss-Of-Coolant Accident conditions based on a coupled experimental/numerical approach, Int. J. Solid Struct. 115 (2017) 190-199. https://doi.org/10.1016/j.ijsolstr.2017.03.016