Evaluation of fuel loading pattern of PWR core using PWR-FUEL code

Iman Kuntoro, S. Pinem, T. M. Sembiring, T. Surbakti
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引用次数: 5

Abstract

The in-core fuel management of a nuclear power plant is a problem of optimization of core parameters such as operation cycle, average fuel burnup and shut down margin for determining a fuel loading pattern to meet the safety and economic aspects. The study is aimed to obtain an optimal fuel loading pattern. Two models of fuel burn up calculations were taken namely equilibrium and transition cores burn up models. The calculations will be carried out by means of computer codes SRAC2006 for cell calculation and PWR-FUEL for the fuel management. The results of keff values at BOC and EOC for each transition core are approximately 1.05 as the input data and the core cycle length is found to be 330 days. The keff values at both BOC and EOC are very near to critical at equilibrium core and the core cycle length is found 360 days. The results of the calculation of neutron flux distribution and power density using the NODAL and FDM methods of the PWR-FUEL the code has the same results. From the results of the neutronic parameter, it is shown that the optimal loading pattern of PWR core can be determined by the PWR-FUEL code either with equilibrium core search or with transition core burnup models. Key words: fuel loading pattern, PWR-FUEL code, operation safety.The in-core fuel management of a nuclear power plant is a problem of optimization of core parameters such as operation cycle, average fuel burnup and shut down margin for determining a fuel loading pattern to meet the safety and economic aspects. The study is aimed to obtain an optimal fuel loading pattern. Two models of fuel burn up calculations were taken namely equilibrium and transition cores burn up models. The calculations will be carried out by means of computer codes SRAC2006 for cell calculation and PWR-FUEL for the fuel management. The results of keff values at BOC and EOC for each transition core are approximately 1.05 as the input data and the core cycle length is found to be 330 days. The keff values at both BOC and EOC are very near to critical at equilibrium core and the core cycle length is found 360 days. The results of the calculation of neutron flux distribution and power density using the NODAL and FDM methods of the PWR-FUEL the code has the same results. From the results of the neutr...
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用PWR- fuel代码评价压水堆堆芯燃料装载方式
核电厂堆芯内燃料管理是对运行周期、平均燃料燃耗和停堆余量等堆芯参数进行优化,以确定满足安全性和经济性要求的燃料加载方式的问题。研究的目的是获得一个最优的燃料加载模式。采用了平衡燃烧模型和过渡燃烧模型两种燃料燃烧计算模型。计算将通过计算机代码SRAC2006进行单元计算和PWR-FUEL进行燃料管理。作为输入数据,每个过渡岩心在BOC和EOC的keff值的结果约为1.05,岩心周期长度为330天。BOC和EOC的keff值都非常接近平衡岩心的临界值,岩心周期长度为360天。用该程序的节点法和FDM法计算中子通量分布和功率密度的结果是一致的。中子参数的计算结果表明,采用平衡堆芯搜索和过渡堆芯燃燃模型均可确定压水堆堆芯的最佳加载模式。关键词:燃料装载方式,PWR-FUEL规则,运行安全。核电厂堆芯内燃料管理是对运行周期、平均燃料燃耗和停堆余量等堆芯参数进行优化,以确定满足安全性和经济性要求的燃料加载方式的问题。研究的目的是获得一个最优的燃料加载模式。采用了平衡燃烧模型和过渡燃烧模型两种燃料燃烧计算模型。计算将通过计算机代码SRAC2006进行单元计算和PWR-FUEL进行燃料管理。作为输入数据,每个过渡岩心在BOC和EOC的keff值的结果约为1.05,岩心周期长度为330天。BOC和EOC的keff值都非常接近平衡岩心的临界值,岩心周期长度为360天。用该程序的节点法和FDM法计算中子通量分布和功率密度的结果是一致的。从中性的结果来看……
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