摘要
反应堆设计中需给出各个参数不确定度,核数据是反应性相关参数不确定度的重要来源。利用SCALE6.1程序中TRITON(Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion)、TSUNAMI-3D(Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in Three Dimensions)和TSAR(Tool for Sensitivity Analysis of Reactivity Responses)模块,结合自带44群协方差数据库,分析了熔盐实验堆反应性相关参数。给出核数据不确定度导致寿期初和寿期末k_(eff)、控制棒价值及温度反应性不确定度分别为522×10~(-5)、506×10~(-5)、96.70×10~(-5)和8.90×10~(-5)。结合灵敏度系数和核数据的标准偏差分析,结果显示:对k_(eff)影响较大的核素及反应道为235U()、(n,γ)、~(238)U(n,γ)、C-graphite(n,el)、~7Li(n,γ)、~(239)Pu()、(n,f)和~(135)Xe(n,γ)等核反应数据;对控制棒价值和温度反应性影响比较大的核素及反应道为~(19)F(n,el)、~(58)Ni(n,γ)、~6Li(n,t)等核反应数据。
[Background] Uncertainty analysis is an essential and mandatory work for reactor design. Nuclear data is an important origin of uncertainty in reactivity parameters. [Purpose] This study aims to obtain and analyze the uncertainty of reactivity parameters and the more significant nuclear data of molten salt experiment reactor.[Methods] The transport rigor implemented with time-dependent operation for neutronic depletion(TRITON), tools for sensitivity and uncertainty analysis methodology implementation in three dimensions(TSUNAMI-3D) and tool for sensitivity analysis of reactivity responses(TSAR) modules of SCALE code are combined with its 44-group covariance data library to analyze the uncertainties of keffat the beginning of life(BOL) and the end of life(EOL),control rod worth(CRW) and temperature coefficients(TC) for molten salt experiment reactor, etc. [Results] The uncertainties are 522 × 10~(-5) and 506 × 10~(-5) for keffat BOL and EOL, and 96.70 × 10~(-5), 8.90 × 10~(-5) for CRW and TC respectively. [Conclusion] The analysis for sensitivity coefficients and covariation data shows that the reaction data of ~(235)U(),(n, γ),~(238)U(n, γ), C-graphite(n, el),~7Li(n, γ),~(239)Pu(),(n, f) and ~(135)Xe(n, γ) are more significant for keff uncertainty, and ~(19)F(n,el),~(58)Ni(n,γ),~6Li(n,t) are important for uncertainties of CRW and TC.
引文
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