UMo/Zr单片式燃料板起泡行为数值模拟
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摘要
燃料板的鼓泡临界温度是制定研究试验堆安全系数的标准之一,通常由鼓泡退火实验确定。针对鼓泡退火实验,本研究发展了一种对UMo/Zr单片式燃料板宏观起泡行为进行计算模拟的方法,并计算分析了气腔内裂变气体原子数对鼓泡高度的影响,获得了包壳内的Mises应力和等效塑性应变随温度升高而演化的规律。研究发现,气腔周围包壳产生塑性变形是起泡的一个关键原因。此研究为燃料板起泡机理和关键影响因素分析打下了基础。
Blister thresholds of fuel plates are a standard to establish the safety margin for research and test reactors.The thresholds are determined by blister anneal test.In this study,a method was developed for simulating the blistering behavior of UMo/Zr monolithic fuel plates during annealing,and the influence of the number of internal fission gas atoms on the blister height was investigated.The evolution laws were obtained for the Mises stresses and the equivalent plastic strains in the cladding.The research results indicate that it is a critical reason for blistering that plastic strains occur in the cladding part surrounding the vacancy.This study lays a foundation for analyzing the mechanism and critical influence factors of blistering behavior.
Blister thresholds of fuel plates are a standard to establish the safety margin for research and test reactors.The thresholds are determined by blister anneal test.In this study,a method was developed for simulating the blistering behavior of UMo/Zr monolithic fuel plates during annealing,and the influence of the number of internal fission gas atoms on the blister height was investigated.The evolution laws were obtained for the Mises stresses and the equivalent plastic strains in the cladding.The research results indicate that it is a critical reason for blistering that plastic strains occur in the cladding part surrounding the vacancy.This study lays a foundation for analyzing the mechanism and critical influence factors of blistering behavior.
引文
[1]ZHAO Y,GONG X,DING S.Simulation of the irradiation-induced thermo-mechanical behaviors evolution in monolithic U-Mo/Zr fuel plates under a heterogeneous irradiation condition[J].Nuclear Engineering and Design,2015,285:84-97.
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[5]KIM Y S,JEONG G Y,PARK J M,et al.Fission induced swelling of U-Mo/Al dispersion fuel[J].Journal of Nuclear Materials,2015,465:142-152.
[6]RICE F J,WACHS D M,ROBINSON A B,et al.U-Mo plate blister anneal interim report[C]∥RERTR 2010.Chicago,Illinois:Argonne National Laboratory,2010.
[7]WACHS D,RICE F,GLAGALENKO I.Blister threshold based thermal limits for the U-Mo monolithic fuel system[C]∥RERTR 2012.Chicago,Illinois:Argonne National Laboratory,2012.
[8]BEESTON J M,HOBBINS R R,GIBSON G W,et al.Development and irradiation performance of uranium aluminide fuels in test reactors[J].Nuclear Technology,1980,49(1):136-149.
[9]OZALTUN H,MILLER S J.Evaluation of blister behavior for U10Mo mini fuel plates with cold rolled foils[C]∥IMECE 2012.USA:American Society of Mechanical Engineers,2012.
[10]SNELGROVE J L.RERTR program progress in qualifying reduced-enrichment fuels[C]∥RERTR1982.Chicago,Illinois:Argonne National Laboratory,1982.
[11]高利军,陈炳德,姜胜耀,等.弥散型燃料板的辐照起泡机理分析[J].原子能科学技术,2012,46(增刊):819-825.GAO Lijun,CHEN Bingde,JIANG Shengyao,et al.Analysis of blistering mechanism for dispersion-type fuel plates during irradiation[J].Atomic Energy Science and Technology,2012,46(Suppl.):819-825(in Chinese).
[12]COPELAND G L,HOFMAN G L,SNELGROVE J L.Irradiation performance of lowenriched uranium fuel elements[C]∥RERTR1984.Chicago,Illinois:Argonne National Laboratory,1984.
[13]ZHAO Y,GONG X,DING S,et al.A numerical method for simulating the non-homogeneous irradiation effects in full-sized dispersion nuclear fuel plates[J].International Journal of Mechanical Sciences,2014,81:174-183.
[14]FISHER E S,RENKEN C J.Single-crystal elastic moduli and the hcp→bcc transformation in Ti,Zr,and Hf[J].Physical Review,1964,135(2A):482-494.
[15]HAGRMAN D L,REYMANN G A C.MATPROversion 11:A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior[M].USA:[s.n.],1979.
[16]SPINO J,REST J,GOLL W,et al.Matrix swelling rate and cavity volume balance of UO2fuels at high burn-up[J].Journal of Nuclear Materials,2005,346(2):131-144.
[2]KIM Y S,HOFMAN G L.Fission product induced swelling of U-Mo alloy fuel[J].Journal of Nuclear Materials,2011,419(1-3):291-301.
[3]MEYER M K,WACHS D M,JUE J F,et al.U.S.progress in the development of very high density low enrichment research reactor fuels[C]∥RRFM 2012.Brussels,Belgium:European Nuclear Society,2012.
[4]KIM Y S,HOFMAN G L,CHEON J S,et al.Fission induced swelling and creep of U-Mo alloy fuel[J].Journal of Nuclear Materials,2013,437(1-3):37-46.
[5]KIM Y S,JEONG G Y,PARK J M,et al.Fission induced swelling of U-Mo/Al dispersion fuel[J].Journal of Nuclear Materials,2015,465:142-152.
[6]RICE F J,WACHS D M,ROBINSON A B,et al.U-Mo plate blister anneal interim report[C]∥RERTR 2010.Chicago,Illinois:Argonne National Laboratory,2010.
[7]WACHS D,RICE F,GLAGALENKO I.Blister threshold based thermal limits for the U-Mo monolithic fuel system[C]∥RERTR 2012.Chicago,Illinois:Argonne National Laboratory,2012.
[8]BEESTON J M,HOBBINS R R,GIBSON G W,et al.Development and irradiation performance of uranium aluminide fuels in test reactors[J].Nuclear Technology,1980,49(1):136-149.
[9]OZALTUN H,MILLER S J.Evaluation of blister behavior for U10Mo mini fuel plates with cold rolled foils[C]∥IMECE 2012.USA:American Society of Mechanical Engineers,2012.
[10]SNELGROVE J L.RERTR program progress in qualifying reduced-enrichment fuels[C]∥RERTR1982.Chicago,Illinois:Argonne National Laboratory,1982.
[11]高利军,陈炳德,姜胜耀,等.弥散型燃料板的辐照起泡机理分析[J].原子能科学技术,2012,46(增刊):819-825.GAO Lijun,CHEN Bingde,JIANG Shengyao,et al.Analysis of blistering mechanism for dispersion-type fuel plates during irradiation[J].Atomic Energy Science and Technology,2012,46(Suppl.):819-825(in Chinese).
[12]COPELAND G L,HOFMAN G L,SNELGROVE J L.Irradiation performance of lowenriched uranium fuel elements[C]∥RERTR1984.Chicago,Illinois:Argonne National Laboratory,1984.
[13]ZHAO Y,GONG X,DING S,et al.A numerical method for simulating the non-homogeneous irradiation effects in full-sized dispersion nuclear fuel plates[J].International Journal of Mechanical Sciences,2014,81:174-183.
[14]FISHER E S,RENKEN C J.Single-crystal elastic moduli and the hcp→bcc transformation in Ti,Zr,and Hf[J].Physical Review,1964,135(2A):482-494.
[15]HAGRMAN D L,REYMANN G A C.MATPROversion 11:A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior[M].USA:[s.n.],1979.
[16]SPINO J,REST J,GOLL W,et al.Matrix swelling rate and cavity volume balance of UO2fuels at high burn-up[J].Journal of Nuclear Materials,2005,346(2):131-144.