NUCLEAR DATA UNCERTAINTY PROPAGATION FOR A TYPICAL PWR FUEL ASSEMBLY WITH BURNUP
NUCLEAR DATA UNCERTAINTY PROPAGATION FOR A TYPICAL PWR FUEL ASSEMBLY WITH BURNUP
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具有燃耗的典型压水堆燃料组件的核数据不确定性传播
DOI：
10.5516/net.01.2014.712
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发表时间：
2014
影响因子：
2.7
通讯作者：
C. Sciolla
中科院分区：
文献类型：
--
作者：
D. Rochman;C. Sciolla
在OECD核能机构建模不确定性分析（UAM）专家工作组的框架下，研究了核数据不确定性对典型压水堆燃料组件模型的影响。将“快速全蒙特卡罗”方法应用于蒙特卡罗输运和燃耗码蛇模型。由于锕系元素和裂变产物的输运截面、裂变产率和热散射数据，得到了燃烧过程中k∞、反应速率、两族截面、库存和局部引脚功率密度的不确定性。
The effects of nuclear data uncertainties are studied on a typical PWR fuel assembly model in the framework of the OECD Nuclear Energy Agency UAM (Uncertainty Analysis in Modeling) expert working group. The “Fast Total Monte Carlo” method is applied on a model for the Monte Carlo transport and burnup code SERPENT. Uncertainties on k∞, reaction rates, two-group cross sections, inventory and local pin power density during burnup are obtained, due to transport cross sections for the actinides and fission products, fission yields and thermal scattering data.