反应引入性事故(RIA)工况下燃料包壳性能堆外试验方法研究综述
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- 英文论文题名：Reviews of mechanical tests to assess cladding performance during a reactivity-initiated accident(RIA)
- 论文作者：张晏玮 ; 王荣山 ; 柏广海 ; 梅金娜 ; 刘二伟 ; 耿建桥
- 英文论文作者：ZHANG Yan-wei ; WANG Rong-shan ; BAI Guang-hai ; MEI Jin-na ; LIU Er-wei ; GENG Jian-qiao ; Suzhou Nuclear Power Research Institute
- 年：2015
- 作者机构：苏州热工研究院有限公司;
- 论文关键词：反应引入性事故 ; 燃料包壳 ; 试验方法 ; 综述
- 英文论文关键词：reactivity-initiated accident(RIA) ; cladding ; mechanical test ; reviews
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第5册（核材料分卷、辐射防护分卷）
- 语种：中文
- 分类号：TL375.6
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：8
- 文件大小：781k
- 原文格式：O
- 会议级别：全国
摘要
文章介绍了燃料包壳在反应引入性事故(RIA)工况下的失效机理及原因,广泛调研了RIA工况下的燃料包壳性能的试验研究方法,对国内外的研究现状进行了评述,比较分析了各试验方法的实际应力状态及优缺点。分析表明,EDC测试以及各种环向拉伸测试的应力状态与RIA工况下包壳的应力状态相差甚远,管材爆破、环向压缩、PSU平面应变拉伸以及磁致膨胀都对应接近RIA工况的不同的应变状态,这些试验的数据需要较少的修正。展望了RIA工况下的燃料包壳性能试验的发展趋势,为我国的燃料包壳材料的研发及性能评价提供参考。
The mechanical test procedures that address fuel cladding failure during a RIA are reviewed with an emphasis on the development of test procedures that determine the deformation and fracture behavior of cladding under conditions similar to those reached in a RIA.An analysis of cladding strain and stress are summarized and advantages and disadvantages of these tests are discussed.The short ring tests as well as EDC tests are quite different from those experienced by cladding during RIA,the burst test,the ring compression tests,the PSU plane-strain tests and the magneto-forming test can provide comparatively small corrections in simulating the stress state of RIA.However,each of these test procedures have limitations in duplicating the precise failure conditions associated with RIA.
The mechanical test procedures that address fuel cladding failure during a RIA are reviewed with an emphasis on the development of test procedures that determine the deformation and fracture behavior of cladding under conditions similar to those reached in a RIA.An analysis of cladding strain and stress are summarized and advantages and disadvantages of these tests are discussed.The short ring tests as well as EDC tests are quite different from those experienced by cladding during RIA,the burst test,the ring compression tests,the PSU plane-strain tests and the magneto-forming test can provide comparatively small corrections in simulating the stress state of RIA.However,each of these test procedures have limitations in duplicating the precise failure conditions associated with RIA.
引文
[1]MACDONALD P E,et al.Assessment of light-water-reactor fuel damage during a reactivity-initiated-accident[J].Nuclear Safety,1980,21(5):582-602.
[2]FUKETA T,et al.RIA-and LOCA-simulating experiments on high burnup LWR fuels,2005.In:IAEA technical meeting on fuel behavior modeling under normal,transient and accident conditions and high burnups,September 58,2005,Kendal,United Kingdom,IAEA.
[3]CHUNG H M,KASSNER T F.Cladding metallurgy and fracture behavior during reactivity-initiated accidents at high burnup[J].Nuclear engineering and design,1998,186(3):411-427.
[4]DESQUINES J,et al.The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident(RIA)[J].Journal of Nuclear Materials,2011,412(2):250-267.
[5]CAZALIS B,et al.The PROMETRA program;fuel cladding mechanical behavior under high strain rate[J].Nuclear technology,2007,157(3):215-229.
[6]KURODA M,et al.Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics[J].Nuclear engineering and design,2001,203(2):185-194.
[7]DAUM R S,et al.Mechanical property testing of irradiated Zircaloy cladding under reactor transient conditions[J].ASTM SPECIAL TECHNICAL PUBLICATION,2002,1418:195-210.
[8]PIERRON O,et al.The influence of hydride blisters on the fracture of Zircaloy-4[J].Journal of Nuclear Materials,2003,322(1):21-35.
[9]KIM J H,et al.Behavior of zirconium fuel cladding under fast pressurization rates[J].Nuclear Engineering and Design,2008,238(6):1441-1447.
[10]GRIGORIEV V,et al.Further development of mechanical test simulate RIA in irradiated cladding,in:24th NSRR Technical Review Meeting(JAERI-Conf 2001-010),Ibaraki-ken,Japan,JAERI,2001,139-49.
[11]KAPLAR E,et al.(2001),Mechanical properties of unirradiated and irradiated Zr-lNb cladding:Procedures and results of low temperature biaxial bursts and axial tensile tests,Report NUREG/IA-0199,US Nuclear Regulatory Commission,Washington DC,USA.
[12]NAGASE F,et al.Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction[J].Journal of nuclear science and technology,2009,46(6):545-552.
[13]SUGIYAMA T,High burnup LWR fuel behavior under RIA conditions,Fuel Safety Research Meeting,Kyoto,Japan,October 7,2005.
[14]BUSSER V,et al.Mechanical response of oxidized Zircaloy-4 cladding material submitted to a ring compression test[J].Journal of Nuclear Materials,2009,384(2):87-95.
[15]LINK T,et al.Failure of Zircaloy cladding under transverse plane-strain deformation[J].Nuclear Engineering and Design,1998,186(3):379-394.
[16]LECLERCQ S,et al.Failure characteristics of cladding tubes under RIA conditions[J].Nuclear Engineering and Design,2008,238(9):2206-2218.
[2]FUKETA T,et al.RIA-and LOCA-simulating experiments on high burnup LWR fuels,2005.In:IAEA technical meeting on fuel behavior modeling under normal,transient and accident conditions and high burnups,September 58,2005,Kendal,United Kingdom,IAEA.
[3]CHUNG H M,KASSNER T F.Cladding metallurgy and fracture behavior during reactivity-initiated accidents at high burnup[J].Nuclear engineering and design,1998,186(3):411-427.
[4]DESQUINES J,et al.The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident(RIA)[J].Journal of Nuclear Materials,2011,412(2):250-267.
[5]CAZALIS B,et al.The PROMETRA program;fuel cladding mechanical behavior under high strain rate[J].Nuclear technology,2007,157(3):215-229.
[6]KURODA M,et al.Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics[J].Nuclear engineering and design,2001,203(2):185-194.
[7]DAUM R S,et al.Mechanical property testing of irradiated Zircaloy cladding under reactor transient conditions[J].ASTM SPECIAL TECHNICAL PUBLICATION,2002,1418:195-210.
[8]PIERRON O,et al.The influence of hydride blisters on the fracture of Zircaloy-4[J].Journal of Nuclear Materials,2003,322(1):21-35.
[9]KIM J H,et al.Behavior of zirconium fuel cladding under fast pressurization rates[J].Nuclear Engineering and Design,2008,238(6):1441-1447.
[10]GRIGORIEV V,et al.Further development of mechanical test simulate RIA in irradiated cladding,in:24th NSRR Technical Review Meeting(JAERI-Conf 2001-010),Ibaraki-ken,Japan,JAERI,2001,139-49.
[11]KAPLAR E,et al.(2001),Mechanical properties of unirradiated and irradiated Zr-lNb cladding:Procedures and results of low temperature biaxial bursts and axial tensile tests,Report NUREG/IA-0199,US Nuclear Regulatory Commission,Washington DC,USA.
[12]NAGASE F,et al.Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction[J].Journal of nuclear science and technology,2009,46(6):545-552.
[13]SUGIYAMA T,High burnup LWR fuel behavior under RIA conditions,Fuel Safety Research Meeting,Kyoto,Japan,October 7,2005.
[14]BUSSER V,et al.Mechanical response of oxidized Zircaloy-4 cladding material submitted to a ring compression test[J].Journal of Nuclear Materials,2009,384(2):87-95.
[15]LINK T,et al.Failure of Zircaloy cladding under transverse plane-strain deformation[J].Nuclear Engineering and Design,1998,186(3):379-394.
[16]LECLERCQ S,et al.Failure characteristics of cladding tubes under RIA conditions[J].Nuclear Engineering and Design,2008,238(9):2206-2218.