燃料棒性能分析软件FRIPAC评估
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摘要
为有效预测燃料棒堆内辐照行为,需将很多复杂物理现象的形成机理与实验观测相结合,建立合理的计算模型。中广核研究院有限公司开发的燃料棒综合性能分析软件FRIPAC考虑了运行过程中物理、化学、材料、热力学、辐照等综合效应对燃料棒性能的影响,可对堆内燃料棒行为进行合理预测。本文介绍了FRIPAC软件的物理模型,通过与实验数据的对比对软件进行了评估。结果显示,FRIPAC能准确预测芯块中心温度和裂变气体释放,验证了FRIPAC模型的正确性。后续将继续开展气腔体积、包壳腐蚀等模型的评估,并基于评估结果不断优化软件模型。
In order to predict the behavior of the fuel rod in reactor, mechanisms and experiment observations of many physical phenomena need to be combined to establish proper calculation models. China Nuclear Power Technology Research Institute Co. Ltd.(CNPRI) recently developed a fuel rod performance analysis code named FRIPAC, which considers the combined effects of physics, chemistry, materials, thermodynamics, irradiation, etc. on the performance of fuel rods during operation. Thus, FRIPAC can predict fuel behavior in reactors reasonably. The physical model of FRIPAC was briefly introduced in this article. The assessment was made based on experimental data. The results show that the prediction of FRIPAC on fuel central temperature and fission gas release is in good agreement with the measured data, which verifies the correctness of the FRIPAC model. For the future work, the FRIPAC is expected to continue with the assessment of internal rod void volume, cladding corrosion, etc. and to continuously optimize the models based on the assessment results.
In order to predict the behavior of the fuel rod in reactor, mechanisms and experiment observations of many physical phenomena need to be combined to establish proper calculation models. China Nuclear Power Technology Research Institute Co. Ltd.(CNPRI) recently developed a fuel rod performance analysis code named FRIPAC, which considers the combined effects of physics, chemistry, materials, thermodynamics, irradiation, etc. on the performance of fuel rods during operation. Thus, FRIPAC can predict fuel behavior in reactors reasonably. The physical model of FRIPAC was briefly introduced in this article. The assessment was made based on experimental data. The results show that the prediction of FRIPAC on fuel central temperature and fission gas release is in good agreement with the measured data, which verifies the correctness of the FRIPAC model. For the future work, the FRIPAC is expected to continue with the assessment of internal rod void volume, cladding corrosion, etc. and to continuously optimize the models based on the assessment results.
引文
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[6] LASSMANN K,BLANK H.Modeling of fuel rod behavior and recent advances of the TRANSURANUS code[J].Nuclear Engineering and Design,1998,106:291-313.
[7] DITTUS F W,BOELTER L M K.Heat transfer in automobile radiators of the tubular type[J].International Communications in Heat & Mass Transfer,1985,12(1):3-22.
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[9] LANNING D D,BEYER C E.FRAPCON-3 updates,including mixed-oxide fuel properties[R].US:PNNL,2005.
[10] NOBLE L D,RIM C S.Background and derivation of ANS-5.4 standard fission product release model[R].US:American Nuclear Society,1982.
[11] SPEIGHT M V.A calculation on the migration of fission gas in material exhibiting precipitation and resolution of gas atoms under irradiation[J].Journal of Nuclear Materials,1969,37:180-185.
[12] 王鑫,申杨.论范氏气体方程和理想气体状态方程的关系[J].大学物理,2010,29(4):8-10.WANG Xin,SHEN Yang.On the relationship between equations of state for van der Waals and ideal gas[J].College Physics,2010,29(4):8-10(in Chinese).
[13] 刘昆元,汪文川.Peng-Robinson状态方程计算含氢系统汽液平衡——超临界气体的参数处理[J].化工学报,1989,40(1):73-81.LIU Kunyuan,WANG Wenchuan.Calculations of vapor-liquid equilibria of hydrogen-containing systems with Peng-Robinson equation of state—Modification of parameters for the supercritical gas[J].Journal of Chemical Industry and Engineering,1989,40(1):73-81(in Chinese).
[2] GEELHOOD K J,LUSCHER W G.FRAPCON-4.0:Integral assessment[R].US:PNNL,2015.
[3] Van UFFELEN P,SCHUBERT A.Verification of the TRANSURANUS fuel performance code:An overview[C]//8th International Conference on WWER Fuel Performance.[S.l.]:[s.n.],2007.
[4] LYON W F,JAHINGIR M N.Fuel analysis and licensing code:FALCON MOD01:Volume 3:Verification and validation[R].US:EPRI,2004.
[5] WILLIAMSON R L,GAMBLE K A.Validating the BISON fuel performance code to integral LWR experiments[J].Nuclear Engineering and Design,2016,301:232-244.
[6] LASSMANN K,BLANK H.Modeling of fuel rod behavior and recent advances of the TRANSURANUS code[J].Nuclear Engineering and Design,1998,106:291-313.
[7] DITTUS F W,BOELTER L M K.Heat transfer in automobile radiators of the tubular type[J].International Communications in Heat & Mass Transfer,1985,12(1):3-22.
[8] HOLMAN J P.Heat transfer[M].Beijing:China Machine Press,2011:35-37.
[9] LANNING D D,BEYER C E.FRAPCON-3 updates,including mixed-oxide fuel properties[R].US:PNNL,2005.
[10] NOBLE L D,RIM C S.Background and derivation of ANS-5.4 standard fission product release model[R].US:American Nuclear Society,1982.
[11] SPEIGHT M V.A calculation on the migration of fission gas in material exhibiting precipitation and resolution of gas atoms under irradiation[J].Journal of Nuclear Materials,1969,37:180-185.
[12] 王鑫,申杨.论范氏气体方程和理想气体状态方程的关系[J].大学物理,2010,29(4):8-10.WANG Xin,SHEN Yang.On the relationship between equations of state for van der Waals and ideal gas[J].College Physics,2010,29(4):8-10(in Chinese).
[13] 刘昆元,汪文川.Peng-Robinson状态方程计算含氢系统汽液平衡——超临界气体的参数处理[J].化工学报,1989,40(1):73-81.LIU Kunyuan,WANG Wenchuan.Calculations of vapor-liquid equilibria of hydrogen-containing systems with Peng-Robinson equation of state—Modification of parameters for the supercritical gas[J].Journal of Chemical Industry and Engineering,1989,40(1):73-81(in Chinese).