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http://dx.doi.org/10.1016/j.net.2018.07.003

Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring  

Khvostov, Grigori (Paul Scherrer Institut)
Publication Information
Nuclear Engineering and Technology / v.50, no.7, 2018 , pp. 1190-1197 More about this Journal
Abstract
Analysis of the GRSW-A model coupled into the FALCON code is extended by simulation of central void formation in fuel pellets due to high-temperature fuel restructuring. The extended calculation is verified against published, well-known experimental data. Good agreement with the data for a central void diameter in pellets of the rod irradiated in an Experimental Breeder Reactor is shown. The new calculation methodology is employed in comparative analysis of modern BWR fuel behavior under assumed high-power operation. The initial fuel porosity is shown to have a major effect on the predicted central void diameter during the operation in question. Discernible effects of a central void on peak fuel temperature and Pellet-Cladding Mechanical Interaction (PCMI) during a simulated power ramp are shown. A mitigating effect on PCMI is largely attributed to the additional free volume in the pellets into which the fuel can creep due to internal compressive stresses during a power ramp.
Keywords
GRSW-A model; FALCON code; High-temperature restructuring; Central void formation;
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  • Reference
1 D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-26711-P1, National Technical Information Services, 1976, pp. 113-144.
2 D.R. O'Boyle, F.L. Brown, J.E. Sanecki, Solid fission product behavior in Uranium-Plutonium oxide fuel irradiated in a fast neutron flux, J. Nucl. Mater. (1969) 27-42.
3 Y.R. Rashid, R.S. Dunham, R.O. Montgomery, FALCON MOD01: Fuel Analysis and Licensing Code - Volume 1: Theoretical and Numerical Bases, EPRI Report 1011307, December 2004.
4 G. Khvostov, A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code, in: Proc.: TOP Fuel 2009, Paris, France, September 6-10, 2009.
5 A. Medvedev, S. Bogatyr, V. Kouznetsov, G. Khvostov, V. Lagovsky, L. Korystin, V. Poudov, Fuel rod behavior at high burnup WWER fuel cycles, in: Proc.: 5th International Conference on WWER Fuel Performance, Modeling and Experimental Support. 29 September - 3 October, Congress Center Albena, Bulgaria, 2003.
6 V.I. Arimescu, I. Vallejo, J. Karlsson, G. Zhou, G. Grandi, P. Raynaud, Y. Yun, N. Doncel, J. Sercombe, M. Pytel, M. Dostal, R. Dunavant, J.S. Yoo, Third SCIP modeling Workshop: beneficial impact of slow power ramp on PCI performance, in: Proc.: Water Reactor Fuel Performance Meeting WRFPM 2014, Sendai, Japan, Sep. 14-17, 2014.
7 L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou, Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project, Nucl. Eng. Des. 241 (2011) 815-825.   DOI
8 Fuel Analysis and Licensing Code: FALCON MOD01: Volume 2: User's Manual, EPRI, Palo Alto, CA, 2004, p. 1011308.
9 G. Ledergerber, S. Valizadeh, J. Wright, M. Limback, L. Hallstadius, D. Gavillet, S. Abolhassani, F. Nagase, T. Sugiyama, W. Wiesenack, T. Tverberg, Fuel behaviour beyond design - exploring the limits, in: Proc.: Water Reactor Fuel Performance Meeting, WRFPM 2008, Seoul, Korea, 19-23 October, 2008.
10 G. Khvostov, W. Wiesenack, Analysis of selected Halden overpressure tests using the FALCON code Nuclear Engineering and Design, Nucl. Eng. Des. 310 (2016) 395-409.   DOI
11 (USNRC SRP 4.2), NUREG-0800 Rev. 3, US Nuclear Regulatory Commission Standard Review Plan 4.2 - Fuel System Design, March 2007.
12 G. Khvostov, A. Medvedev, S. Bogatyr, The dynamic model of grain boundary processes in high burn-up LWR fuel and its application in analysis by the START-3 code, in: Proc.: International Conference on WWER Fuel Performance, Modeling and Experimental Support, Albena-Varna, Bulgaria, September 29-October 3, 2003.
13 V. Novikov, A. Medvedev, G. Khvostov, S. Bogatyr, V. Kuznetsov, L. Korystin, Modelling of thermal mechanical behaviour of high burn-up VVER fuel at power transients with especial emphasis on impact of fission gas induced swelling of fuel pellets, in: Proc.: OECD Seminar on Pellet-clad Interaction in Light Water Reactor Fuels, AIX EN PROVENCE, France, March 9-11, 2004.
14 Zhengang Duan, Huilong Yang, Yuhki Satoh, Kenta Murakami, Sho Kano, Zishou Zhao, Jingjie Shen, Hiroaki Abe, Current status of materials development of nuclear fuel cladding tubes for light water reactors, Nucl. Eng. Des. 316 (2017) 131-150.   DOI
15 C. Cozzo, S. Rahman, SiC cladding thermal conductivity requirements for normal operation and LOCA conditions, PNE (Protein Nucleic Acid Enzyme) 106 (2018) 278-283.
16 G. Khvostov, K. Mikityuk, M.A. Zimmermann, A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code, Nucl. Eng. Des. 241 (2011) 2983-3007.   DOI
17 J.B. Ainscough, B.W. Oldfield, J.O. Ware, Isothermal grain growth kinetics in sintered $UO_2$ pellets, J. Nucl. Mater. 49 (1974) 117-128.
18 Michael R. Tonks, Yongfeng Zhang, Xianming Bai, Paul C. Millett, Demonstrating the Temperature Gradient Impact on Grain Growth in $UO_2$ Using the Phase Field Method, Materials Research Letters (2013), https://doi.org/10.1080/21663831.2013.849300.
19 F. Ribeiro, G. Khvostov, Multi-scale approach to advanced fuel modelling for enhanced safety, Prog. Nucl. Energy 84 (2015) 24-35.   DOI