N36锆合金包壳辐照生长经验模型研究
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摘要
利用N36锆合金包壳燃料棒堆内辐照考验的部分池边检查数据,计算了4个典型辐照生长经验模型对N36锆合金包壳的适用参数。计算结果表明,在典型辐照生长经验模型中,双曲正切经验模型最适合描述N36锆合金包壳辐照生长行为。在双曲正切经验模型基础上,建立了N36锆合金包壳辐照生长最佳估算模型和包络模型。通过添加工程因子,建立了不同加工工艺的N36锆合金包壳辐照生长经验模型。利用池边检查剩余数据对N36锆合金包壳辐照生长经验模型进行了验证,模型与数据吻合较好。
The parameters of four typical irradiated growth experience models for N36 zirconium alloy cladding were calculated by using partial pool side examination data of N36 zirconium alloy cladding fuel rods in the reactor. The results show that the hyperbolic tangent empirical model is the most suitable for describing the irradiation growth behavior of N36 zirconium alloy cladding in four typical irradiation growth experience models. Based on the hyperbolic tangent empirical model, the nominal model and bound model for the irradiation growth of N36 zirconium alloy cladding were established. By adding engineering factors, the experience model of irradiation growth for N36 zirconium alloy cladding with different processing technologies was established. The experience model of N36 zirconium alloy cladding was validated by using the rest data of the pool side examination, and the model is in good agreement with the data.
The parameters of four typical irradiated growth experience models for N36 zirconium alloy cladding were calculated by using partial pool side examination data of N36 zirconium alloy cladding fuel rods in the reactor. The results show that the hyperbolic tangent empirical model is the most suitable for describing the irradiation growth behavior of N36 zirconium alloy cladding in four typical irradiation growth experience models. Based on the hyperbolic tangent empirical model, the nominal model and bound model for the irradiation growth of N36 zirconium alloy cladding were established. By adding engineering factors, the experience model of irradiation growth for N36 zirconium alloy cladding with different processing technologies was established. The experience model of N36 zirconium alloy cladding was validated by using the rest data of the pool side examination, and the model is in good agreement with the data.
引文
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[9] 王朋飞,赵文金,戴训. N36锆合金管材的织构研究[J]. 钛工业进展,2016,33(3):38-41. WANG Pengfei, ZHAO Wenjin, DAI Xun. Study on texture of N36 zirconium alloy tube[J]. Titanium Industry Progress, 2016, 33(3): 38-41(in Chinese).
[2] BERNA G A, BEYER G A, DAVIS K L, et al. FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup[R]. US: Nuclear Regulatory Commission, 1997.
[3] GEELHOOD K J, LUSCHER W G, BEYER C E, et al. FRAPCON-3.4: A computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup[R]. US: Nuclear Regulatory Commission, 2011.
[4] JACOUD J L. Description and qualification of the COPERNIC/TRANSURANUS fuel rod design code, TFJC-DC-1556[R]. [S. l.]: [s. n.], 2000.
[5] SUZUKI M, SAITOU H, UDAGAWA Y, et al. Light water reactor fuel analysis code FEMAXI-7: Model and structure[M]. Nihon: Nihon GenshiryokuKenkyū Kaihatsu Kikō, 2013.
[6] PEREZ D M, WILLIAMSON R L, NOVASCONE S R, et al. Assessment of BISON: A nuclear fuel performance analysis code[R]. Idaho Falls: Idaho National Laboratory, 2013.
[7] MARINO A C, SAVINO E J, HARRIAGUE S. BACO (BArraCOmbustible) code version 2.20: A thermo-mechanical description of a nuclear fuel rod[J]. Journal of Nuclear Materials, 1996, 229: 155-168.
[8] GRIFFITHS M, GILBERT R W. In Fidleris V accelerated irradiation growth of zirconium alloys[C]//Eighth International Symposium on Zirconium in the Nuclear Industry. Philadelphia P A: American Society for Testing and Materials, 1989.
[9] 王朋飞,赵文金,戴训. N36锆合金管材的织构研究[J]. 钛工业进展,2016,33(3):38-41. WANG Pengfei, ZHAO Wenjin, DAI Xun. Study on texture of N36 zirconium alloy tube[J]. Titanium Industry Progress, 2016, 33(3): 38-41(in Chinese).