一种用芯内中子探测器读数校准燃耗后堆芯截面参数的方法  

A CALIBRATION METHOD OF CORE PARAMETERS AFTER BURNUP BY USING LN-CORE NEUTRON DETECTOR READINGS

作　　者：王亚奇[1] 李富[1] 罗征培[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《核科学与工程》1999年第4期349-354,共6页Nuclear Science and Engineering

基　　金：国家自然科学基金!19675021

摘　　要：燃耗后的反应堆堆芯截面参数偏离了原来的数值，尽管用燃耗表对其进行了修正，但由于修正过程中的近似，仍使得截面参数的可靠性受到怀疑。文中提出：在用芯内中子探测器读数重构出“测量的”全堆热群中子通量密度分布的基础上，约束堆芯截面参数，并采用节块格林函数法对其进行校准的一套完整方法。截面参数经校准后，可以使理论模型计算结果与实际测量值相一致。仿真结果说明了此方法的可行性。For a reactor after burn--up, its core parameters deviate from their original values. Even though they have been corrected via burn--up table, the approximation still makes their reliability suspected for the calculated neutron flux density distribution. Based on the 'measured' neutron flux density distribution reconstructed by using harmonics synthesis method (HSM) from the readings of in-core neutron detectors and some necessary restrictions of core parameters, a procedure is proposed to calibrate the core parameters after burn-up. With the calibrated core parameters, the core model calculation would agree well with the measurement data. Some simulations have demonstrated the feasibility of this method.

关 键 词：中子通量密度分布 谐波综合法 反向计算 堆芯截面参数校准 节块格林函数法 

分 类 号：TL421.1[核科学技术—核技术及应用] TL375.19