Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions

被引:13
作者
Jernkvist, Lars O. [1 ]
机构
[1] Quantum Technol AB, Uppsala Sci Pk, S-75183 Uppsala, Sweden
关键词
IRRADIATION-INDUCED RECRYSTALLIZATION; GRAIN-BOUNDARY DIFFUSION; RIM STRUCTURE FORMATION; HIGH-BURNUP STRUCTURE; EQUATION-OF-STATE; NUCLEAR-FUEL; URANIUM-DIOXIDE; SURFACE-ENERGY; INTERGRANULAR FRACTURE; MOLECULAR-DYNAMICS;
D O I
10.1051/epjn/2019030
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.
引用
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页数:29
相关论文
共 164 条
[1]  
[Anonymous], 2019, INT FUEL PERF EXP IF
[2]  
[Anonymous], SOLID MECH ITS APPL
[3]  
[Anonymous], 2019, PRESS WAT REACT CONT
[4]  
[Anonymous], 2014, FIN REP COORD RES PR, V1
[5]  
[Anonymous], 2001, SCDAP RELAP5 MOD 3 3
[6]  
[Anonymous], 2005, FRACTURE MECH FUNDAM
[7]  
[Anonymous], 2010, 6847 OECD NUCL EN AG
[8]   Advanced doped UO2 pellets in LWR applications [J].
Arborelius, Jakob ;
Backman, Karin ;
Hallstadius, Lars ;
Limbaeck, Magnus ;
Nilsson, Jimmy ;
Rebensdorff, Bjoern ;
Zhou, Gang ;
Kitano, Koji ;
Loefstroem, Reidar ;
Roennberg, Gunnar .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (09) :967-976
[9]   FISSION-GAS BUBBLE DISTRIBUTION IN URANIUM-DIOXIDE FROM HIGH-TEMPERATURE IRRADIATED SGHWR FUEL PINS [J].
BAKER, C .
JOURNAL OF NUCLEAR MATERIALS, 1977, 66 (03) :283-291
[10]   EVALUATION OF FISSION-GAS RELEASE IN HIGH-BURNUP LIGHT WATER-REACTOR FUEL-RODS [J].
BARNER, JO ;
CUNNINGHAM, ME ;
FRESHLEY, MD ;
LANNING, DD .
NUCLEAR TECHNOLOGY, 1993, 102 (02) :210-231