Browse > Article
http://dx.doi.org/10.1016/j.net.2021.04.020

Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)  

Kim, Jinsu (Department of Mechanical Engineering, Korea Advanced Institute of Science and Technology)
Yoon, Jeong Whan (Department of Mechanical Engineering, Korea Advanced Institute of Science and Technology)
Kim, Hyochan (ATF Technology Development Division, Korea Atomic Energy Research Institute)
Lee, Sung-Uk (ATF Technology Development Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.53, no.10, 2021 , pp. 3379-3397 More about this Journal
Abstract
In this study, a multi-physics modeling method was developed to analyze a nuclear fuel rod's thermo-mechanical behavior especially for high temperature anisotropic creep deformation during ballooning and burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer and nonlinear mechanical analysis, the present work newly incorporated the nuclear fuel rod's special characteristics which include gap heat transfer, temperature and burnup dependent material properties, and especially for high temperature creep with material anisotropy. The proposed method was tested through various benchmark analyses and showed good agreements with analytical solutions. From the validation study with a cladding burst experiment which postulates the LOCA scenario, it was shown that the present development could predict the ballooning and burst behaviors accurately and showed the capability to predict anisotropic creep behavior during the LOCA. Moreover, in order to verify the anisotropic creep methodology proposed in this study, the comparison between modeling and experiment was made with isotropic material assumption. It was found that the present methodology with anisotropic creep could predict ballooning and burst more accurately and showed more realistic behavior of the cladding.
Keywords
Loss of coolant accident; Ballooning and burst; Multi-physics nuclear fuel rod; Zircaloy-4 cladding; Anisotropic creep;
Citations & Related Records
연도 인용수 순위
  • Reference
1 R. Morrell, Handbook of Properties of Technical and Engineering Ceramics, Hmso, 1989.
2 F.K.G. Odqvist, Theory of Creep under the Action of Combined Stresses with Applications to High Temperature Machinery, Generalstabens litografiska anstalts forlag, 1936.
3 R. Williamson, K. Gamble, D. Perez, S. Novascone, G. Pastore, R. Gardner, J. Hales, W. Liu, A. Mai, Validating the BISON fuel performance code to integral LWR experiments, Nucl. Eng. Des. 301 (2016) 232-244.   DOI
4 J. Moore, R. Graves, W. Fulkerson, D. McElroy, The Physical Properties of Tungsten, in: 1965 Conference on Thermal Conductivity, Denver, Colorado, 1965.
5 G.S. Was, D. Petti, S. Ukai, S. Zinkle, Materials for future nuclear energy systems, J. Nucl. Mater. 527 (2019), 151837.   DOI
6 J. Crank, P. Nicolson, A practical method for numerical evaluation of solutions of partial differential equations of the heat-conduction type, in: Mathematical Proceedings of the Cambridge Philosophical Society, Cambridge University Press, 1947, pp. 50-67.
7 F. Erbacher, H. Neitzel, H. Rosinger, H. Schmidt, K. Wiehr, Burst criterion of Zircaloy fuel claddings in a loss-of-coolant accident, in: Zirconium in the Nuclear Industry, ASTM International, 1982.
8 W. Wen, L. Capolungo, C.N. Tome, Mechanism-based modeling of solute strengthening: application to thermal creep in Zr alloy, Int. J. Plast. 106 (2018) 88-106.   DOI
9 J.C. Nagtegaal, N. Rebelo, On the development of a general purpose finite element program for analysis of forming processes, Int. J. Numer. Methods Eng. 25 (1988) 113-131.   DOI
10 R. Williamson, J. Hales, S. Novascone, M. Tonks, D. Gaston, C. Permann, D. Andrs, R. Martineau, Multidimensional multiphysics simulation of nuclear fuel behavior, J. Nucl. Mater. 423 (2012) 149-163.   DOI
11 P. Van Uffelen, J. Hales, W. Li, G. Rossiter, R. Williamson, A review of fuel performance modelling, J. Nucl. Mater. 516 (2019) 373-412.   DOI
12 E.B.Y. Touloukian, Specific heat: nonmetallic solids, Thermophysical Properties Matter 5 (1970) 24.
13 J.C. Simo, T.J. Hughes, Computational Inelasticity, Springer Science & Business Media, New York, 2006.
14 D.-H. Kim, G.-H. Choi, H. Kim, C. Lee, S.-U. Lee, J.-D. Hong, H.-S. Kim, Measurement of Zircaloy-4 cladding tube deformation using a three-dimensional digital image correlation system with internal transient heating and pressurization, Nucl. Eng. Des. 363 (2020), 110662.   DOI
15 K. Geelhood, W. Luscher, C. Beyer, J. Cuta, FRAPTRAN 1.4: A Computer Code for the Transient Analysis of Oxide Fuel Rods, US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2011, p. 1. NUREG/CR-7023.
16 G. Thouvenin, B. Michel, J. Sercombe, D. Plancq, P. Thevenin, Multidimensional modeling of a ramp test with the PWR fuel performance code ALCYONE, in: Proceedings of the 2007 LWR Fuel Performance Meeting/TopFuel 2007'Zero by 2010, 2007.
17 J.-M. Ricaud, N. Seiler, G. Guillard, Multi-pin ballooning during LOCA transient: a three-dimensional analysis, Nucl. Eng. Des. 256 (2013) 45-55.   DOI
18 G. Pastore, S. Novascone, R. Williamson, J. Hales, B. Spencer, D. Stafford, Modelling of fuel behaviour during loss-of-coolant accidents using the BISON code, in: Idaho National Lab. (INL), Idaho Falls, United States, 2015.
19 S. Bascou, O. De Luze, S. Ederli, G. Guillard, Development and validation of the multi-physics DRACCAR code, Ann. Nucl. Energy 84 (2015) 1-18.   DOI
20 A. Hellouin de Menibus, J. Sercombe, Q. Auzoux, C. Poussard, Thermomechanical loading applied on the cladding tube during the pellet cladding mechanical interaction phase of a rapid reactivity initiated accident, J. Nucl. Mater. 453 (2014) 210-213.   DOI
21 T. Belytschko, W.K. Liu, B. Moran, K. Elkhodary, Nonlinear Finite Elements for Continua and Structures, John Wiley & Sons, Chichester, 2013.
22 Y. Zhou, B. Devarajan, K.L. Murty, Short-term rupture studies of Zircaloy-4 and Nb-modified Zircaloy-4 tubing using closed-end internal pressurization, Nucl. Eng. Des. 228 (2004) 3-13.   DOI
23 A.A. Rezwan, M.R. Tonks, M.P. Short, Evaluations of the performance of multimetallic layered composite cladding for the light water reactor accident tolerant fuel, J. Nucl. Mater. 535 (2020), 152136.   DOI
24 Y. Deng, K. Shirvan, Y. Wu, G. Su, Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts, J. Nucl. Mater. 516 (2019) 271-288.   DOI
25 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: MATPROeA Library of Materials Properties for Light-Water-Reactor Accident Analysis, Idaho National Engineering Laboratory, 1993.
26 N. Kikuchi, Finite Element Methods in Mechanics, Cambridge University Press, New York, 1986.
27 F. Norton, Creep of High Temperatures, in: McGraw Hill, New York, 1929.
28 A. Ross, R. Stoute, Heat Transfer Coefficient between UO 2 and Zircaloy-2, in Atomic Energy of Canada Limited, 1962.
29 E.H. Kennard, Kinetic Theory of Gases, McGraw-Hill, New York, 1938.
30 D. Lanning, C. Hann, Review of methods applicable to the calculation of gap conductance in Zircaloy-clad UO2 fuel rods, in: Battelle Pacific Northwest Labs., Richland, United States, 1975.
31 R. Hill, The Mathematical Theory of Plasticity, Oxford university press, New York, 1998.
32 C.P. Massey, K.A. Terrani, S.N. Dryepondt, B.A. Pint, Cladding burst behavior of Fe-based alloys under LOCA, J. Nucl. Mater. 470 (2016) 128-138.   DOI
33 J.W. Yoon, D.Y. Yang, K. Chung, Elasto-plastic finite element method based on incremental deformation theory and continuum based shell elements for planar anisotropic sheet materials, Comput. Methods Appl. Mech. Eng. 174 (1999) 23-56.   DOI
34 Dassault Systemes Simulia Corporation, Abaqus Analysis User's Guide, 2014.
35 H. Rosinger, J. Bowden, R. Shewfelt, The anisotropic creep behaviour of Zircaloy-4 fuel cladding at 1073 K, in: Atomic Energy of Canada Ltd., 1982.
36 J.C. Simo, R.L. Taylor, Consistent tangent operators for rate-independent elastoplasticity, Comput. Methods Appl. Mech. Eng. 48 (1985) 101-118.   DOI
37 N. Bhatnagar, V. Arya, Large strain creep analysis of thick-walled cylinders, Int. J. Non Lin. Mech. 9 (1974) 127-140.   DOI
38 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.   DOI
39 R. Thieurmel, J. Besson, E. Pouillier, A. Parrot, A. Ambard, A.-F. Gourgues-Lorenzon, Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient, J. Nucl. Mater. 527 (2019), 151815.   DOI