先进的压水堆燃料管理计算方法研究及软件研制  

Research on Advanced Pressurized Water Reactor Fuel Management Calculation Method and Program Development

作　　者：曹良志[1] 谢仲生[1] 吴宏春[1] 廖承奎[1] 孔德萍 吴锡锋 

机构地区：[1]西安交通大学能源与动力工程学院,西安710049 [2]秦山核电公司技术支持处

出　　处：《西安交通大学学报》2003年第5期519-522,共4页Journal of Xi'an Jiaotong University

基　　金：国家自然科学基金资助项目 (1 990 1 0 2 6 )

摘　　要：利用一种新的正交基函数展开中子通量密度,发展了先进的非线性迭代半解析节块方法,并成功地应用了等效均匀化理论来求解中子扩散方程.以穿透概率方法为基础,依照等效均匀化理论的要求计算了燃料组件和围板/反射层的等效均匀化参数.研制了相应的具有热工等反馈的两群三维压水堆(PWR)燃料管理计算软件包(RTPFAP/RSIM),克服了传统程序基于1 5群、采用反照率边界条件的不足.利用该软件包对秦山一期核电厂前4个循环进行了跟踪计算.结果表明,计算精度满足工程要求,与实测值相比,临界硼质量分数的偏差在±50×10-6以内,堆芯在额定功率运行时,功率分布偏差在±5%以内.To solve the in-core neutron diffusion equation, an advanced nonlinear iteration semi-analysis nodal method is developed, in which a new orthogonal basic function set is chosen for the neutron flux expansion. Based on the transmission probability method, the equivalent homogenization parameters of fuel assembly and baffle/reflector are calculated according to the requirement of the equivalent homogenization theory. An integrated computer program system for the pressurized water reactor (PWR) fuel management calculation (RTPFAP/RSIM) is developed with thermal-hydraulic and many other feedback functions. RTPFAP/RSIM overcomes the disadvantages of using 1.5 groups and albedo. The system is applied to perform the load following calculations of the first 4 cycles in Qinshan Nuclear Power Plant (QNPP). The numerical results show that the accuracy meets the engineering requirements. The calculated ones are compared with the measured ones, and the error of critical boron concentration is less than 50 μg &middotg-1 and the error of power distribution in the rated power is less than 5%.

关 键 词：燃料管理 压水堆 计算方法 软件包 

分 类 号：TL329.2[核科学技术—核技术及应用]