A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions

被引:42
作者
Capps, Nathan [1 ]
Jensen, Colby [2 ]
Cappia, Fabiola [2 ]
Harp, Jason [1 ]
Terrani, Kurt [1 ]
Woolstenhulme, Nicolas [2 ]
Wachs, Daniel [2 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[2] Idaho Natl Lab, Idaho Falls, ID 83401 USA
关键词
FISSION-GAS RELEASE; UO2; NUCLEAR-FUEL; RIM-STRUCTURE FORMATION; UP UO2; THERMAL-CONDUCTIVITY; MICROSTRUCTURAL CHANGE; ELECTRON-MICROSCOPY; DENSITY-ESTIMATION; YOUNGS MODULUS; PCI ANALYSIS;
D O I
10.1016/j.jnucmat.2020.152750
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
High burnup fuel in excess of-6268 GWd/MTU has been observed to severely fragment when subjected to temperature transient conditions as in a loss-of-coolant accident. In the event of cladding failure, the severely fragmented fuel can relocate into the balloon region and potentially disperse through the burst opening into the reactoraeuroTMs primary system. This observation has led to implementation of several independent test programs designed to focus on various aspects of fuel fragmentation, relocation, and dispersal. The purpose of this review is to perform a critical, holistic assessment of fuel fragmentation, relocation, and dispersal under loss-of-coolant conditions to identify data gaps in the experimental data base. Phenomena have been identified and well defined through the various testing programs, and general agreement regarding the governing parameters (temperature, burnup, heating rate, cladding deformation, etc.) has been established. However, there is a significant data gap connecting research to commercial application. Furthermore, previous research attempted to evaluate the problem holistically, but has yet to provide a comprehensive understanding of the problem. Major identified data gaps consist of (1) a comprehensive understanding of pretransient fuel rod conditions (fuel temperature, fuel stress, rod internal pressures, microstructure, etc.), (2) definition of prototypic loss-of-coolant accident conditions (heating rate, fuel temperatures, fuel stress), (3) identification of the differences between nuclear and electrical integral loss-of-coolant accident tests, and connection of fuel rod performance (cladding ballooning, burst opening, potential relocation, fragmentation susceptibility, etc.) to fuel fragmentation, relocation, and dispersal severity. The content of this manuscript provides a clear path for connecting testing and data acquisition to commercial application by providing concrete means for filling data gaps and prioritized testing regimes. (C) 2020 Elsevier B.V. All rights reserved.
引用
收藏
页数:27
相关论文
共 137 条
[1]  
Aleshin Y., 2010, P TOP FUEL 2010 ORL
[2]  
Allision C. M., 1993, NUREGCR6150, VIV
[3]   Thermal conductivities of irradiated UO2 and (U, Gd)O2 pellets [J].
Amaya, M ;
Hirai, M ;
Sakurai, H ;
Ito, K ;
Sasaki, M ;
Nomata, T ;
Kamimura, K ;
Iwasaki, R .
JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (01) :57-64
[4]  
[Anonymous], 2016, REP FUEL FRAGM REL D, P16
[5]  
[Anonymous], 2001, U. S. Nuclear Regulatory Commission, Division of Systems Analysis and Regulatory Effectiveness,
[6]  
[Anonymous], 2008, NUREGCR6967
[7]  
[Anonymous], 1983, Final report. KFK-3346.
[8]  
[Anonymous], IFA6501
[9]  
[Anonymous], NUREG0900
[10]  
[Anonymous], 2006, PCI ANAL STARTUP RAM