中国实验快堆某辐照实验组件燃耗分布测量
|
摘要
在中国实验快堆(CEFR)上建立了实验组件燃耗分布测量的实验装置。对CEFR某一辐照实验组件中的4#及6#燃料元件棒进行了相对燃耗分布的测量,并与理论计算结果进行了比较。结果表明:两根燃料元件棒虽处于实验组件的不同位置,但相对燃耗分布基本一致;燃耗分布的实验测量结果与理论计算结果符合较好;实验组件燃耗分布测量的相对误差在10.2%以内。本文工作为开展快堆乏燃料组件燃耗测量奠定了基础。
An experimental device for measuring the burn-up distribution of test subassembly was established on the China Experimental Fast Reactor(CEFR). The relative burn-up distributions of the 4# and 6# fuel element rods in a certain test subassembly were measured and compared with the theoretical calculation results. The results show that although the two fuel element rods are in different positions of the test subassembly, the relative burn-up distributions are basically the same. The experimental measurement results of the burn-up distribution are in good agreement with the theoretical calculation results. The relative error of the burn-up distribution measurement is less than 10.2%. The work of this paper lays the foundation for the burn-up measurement of fast reactor spent fuel assemblies.
An experimental device for measuring the burn-up distribution of test subassembly was established on the China Experimental Fast Reactor(CEFR). The relative burn-up distributions of the 4# and 6# fuel element rods in a certain test subassembly were measured and compared with the theoretical calculation results. The results show that although the two fuel element rods are in different positions of the test subassembly, the relative burn-up distributions are basically the same. The experimental measurement results of the burn-up distribution are in good agreement with the theoretical calculation results. The relative error of the burn-up distribution measurement is less than 10.2%. The work of this paper lays the foundation for the burn-up measurement of fast reactor spent fuel assemblies.
引文
[1] 杨晓燕,喻宏,刚直.中国实验快堆首次临界装料方案研究[J].原子能科学技术,2013,47(增刊):58-61.YANG Xiaoyan,YU Hong,GANG Zhi.Loading scheme research on the first criticality of China Experimental Fast Reactor[J].Atomic Energy Science and Technology,2013,47(Suppl.):58-61(in Chinese).
[2] MATZKE H.On the rim effect in high burnup UO2 LWR fuels[J].Journal of Nuclear Materials,1992,189(1):141-148.
[3] LASSMANN K,O’CARROLL C,LAAR J V D,et al.The radial distribution of plutonium in high burnup UO2 fuels[J].Journal of Nuclear Materials,1994,208(3):223-231.
[4] 金惠民,刘大鸣,董明礼,等.动力堆乏燃料组件的非破坏性分析[J].原子能科学技术,1996,30(2):185-191.JIN Huimin,LIU Daming,DONG Mingli,et al.Non-destructive analysis of spent fuel assemblies in power reactors[J].Atomic Energy Science and Technology,1996,30(2):185-191(in Chinese).
[5] LEDERGERBER G,ABOLHASSANI S,LIMB?CK M,et al.Characterization of high burnup fuel for safety related fuel testing[J].Journal of Nuclear Science & Technology,2006,43(9):1 006-1 014.
[6] KAITO T,UKAI S,POVSTYANKO A,et al.Fuel pin irradiation test at up to 5 at% burnup in BOR-60 for oxide-dispersion-strengthened ferritic steel claddings[J].Journal of Nuclear Science & Technology,2009,46(6):529-533.
[7] BORODKIN P G,BORODKIN G I,KHRENNIKOV N N.Application of integral ex-core and differential in-core neutron measurements for adjustment of fuel burn-up distributions in VVER-1000[C]//First International Conference on Advancements in Nuclear Instrumentation Measurement Methods & Their Applications.[S.l.]:[s.n.],2010.
[8] BINH D Q,HUY N Q,LAN N P,et al.A method for determining the fuel burn-up distribution of nuclear research reactors by measurements at subcritical states[J].Annals of Nuclear Energy,1997,24(15):1 233-1 240.
[9] SUZAKI T,OKAZAKI S,OKASHITA H,et al.Non-destructive and destructive measurements on burnup characteristics of Japan Power Demonstration Reactor-Ⅰ full-core fuel assemblies[J].Journal of Nuclear Science & Technology,1986,23(1):53-72.
[10] GINTING A B,PENG H L.Absolute burnup measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique[J].Annals of Nuclear Energy,2015,85:613-620.
[11] OWEN T D.Measurement of power and burn-up in irradiated nuclear reactor fuel by a non-destructive method[J].British Journal of Applied Physics,DOI:10.1088/0508-3443/14/7/321.
[12] REILLY D,ENSSLIN N,SMITH H,Jr.,et al.Passive nondestructive assay of nuclear materials,NUREG/CR-5550(LA-UR-90-732)[R].[S.l.]:[s.n.],1991.
[13] NAVARRO J,ARYAEINEJAD R,NIGG D W.A feasibility study to determine cooling time and burnup of ATR fuel using a nondestructive technique and three types of gamma-ray detectors[J].Journal of Astm International,2012,9(3):1-16.
[14] 张肇源,韩传斌,梁克周.用γ扫描测量相对燃耗分布[J].核科学与工程,1983,3(1):93-96.ZHANG Zhaoyuan,HAN Chuanbin,LIANG Kezhou.Measurement of relative fuel consumption distribution by gamma scanning[J].Chinese Journal of Nuclear Science and Engineering,1983,3(1):93-96(in Chinese).
[15] 王新哲.行波堆堆芯中子学及燃耗计算程序Mx_o程序使用说明[R].北京:中国原子能科学研究院快堆设计研究部,2015.
[2] MATZKE H.On the rim effect in high burnup UO2 LWR fuels[J].Journal of Nuclear Materials,1992,189(1):141-148.
[3] LASSMANN K,O’CARROLL C,LAAR J V D,et al.The radial distribution of plutonium in high burnup UO2 fuels[J].Journal of Nuclear Materials,1994,208(3):223-231.
[4] 金惠民,刘大鸣,董明礼,等.动力堆乏燃料组件的非破坏性分析[J].原子能科学技术,1996,30(2):185-191.JIN Huimin,LIU Daming,DONG Mingli,et al.Non-destructive analysis of spent fuel assemblies in power reactors[J].Atomic Energy Science and Technology,1996,30(2):185-191(in Chinese).
[5] LEDERGERBER G,ABOLHASSANI S,LIMB?CK M,et al.Characterization of high burnup fuel for safety related fuel testing[J].Journal of Nuclear Science & Technology,2006,43(9):1 006-1 014.
[6] KAITO T,UKAI S,POVSTYANKO A,et al.Fuel pin irradiation test at up to 5 at% burnup in BOR-60 for oxide-dispersion-strengthened ferritic steel claddings[J].Journal of Nuclear Science & Technology,2009,46(6):529-533.
[7] BORODKIN P G,BORODKIN G I,KHRENNIKOV N N.Application of integral ex-core and differential in-core neutron measurements for adjustment of fuel burn-up distributions in VVER-1000[C]//First International Conference on Advancements in Nuclear Instrumentation Measurement Methods & Their Applications.[S.l.]:[s.n.],2010.
[8] BINH D Q,HUY N Q,LAN N P,et al.A method for determining the fuel burn-up distribution of nuclear research reactors by measurements at subcritical states[J].Annals of Nuclear Energy,1997,24(15):1 233-1 240.
[9] SUZAKI T,OKAZAKI S,OKASHITA H,et al.Non-destructive and destructive measurements on burnup characteristics of Japan Power Demonstration Reactor-Ⅰ full-core fuel assemblies[J].Journal of Nuclear Science & Technology,1986,23(1):53-72.
[10] GINTING A B,PENG H L.Absolute burnup measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique[J].Annals of Nuclear Energy,2015,85:613-620.
[11] OWEN T D.Measurement of power and burn-up in irradiated nuclear reactor fuel by a non-destructive method[J].British Journal of Applied Physics,DOI:10.1088/0508-3443/14/7/321.
[12] REILLY D,ENSSLIN N,SMITH H,Jr.,et al.Passive nondestructive assay of nuclear materials,NUREG/CR-5550(LA-UR-90-732)[R].[S.l.]:[s.n.],1991.
[13] NAVARRO J,ARYAEINEJAD R,NIGG D W.A feasibility study to determine cooling time and burnup of ATR fuel using a nondestructive technique and three types of gamma-ray detectors[J].Journal of Astm International,2012,9(3):1-16.
[14] 张肇源,韩传斌,梁克周.用γ扫描测量相对燃耗分布[J].核科学与工程,1983,3(1):93-96.ZHANG Zhaoyuan,HAN Chuanbin,LIANG Kezhou.Measurement of relative fuel consumption distribution by gamma scanning[J].Chinese Journal of Nuclear Science and Engineering,1983,3(1):93-96(in Chinese).
[15] 王新哲.行波堆堆芯中子学及燃耗计算程序Mx_o程序使用说明[R].北京:中国原子能科学研究院快堆设计研究部,2015.