摘要
为量化燃耗信任制中燃耗计算传递给临界计算的不确定度,本文基于参数统计法对燃耗计算的核素偏差及偏差不确定度展开分析,并以蒙特卡罗(MC)抽样方法计算的k_(inf)不确定度为基准,比较不同抽样方法对临界计算不确定度的影响。结果表明,核素偏差与偏差不确定度是随样品燃耗变化的分段函数。对于临界计算,拉丁超立方抽样(LHS)方法与MC抽样方法的k_(inf)不确定度计算结果吻合较好,且LHS方法可考虑参数间的相关性,计算结果更真实,可进一步提升电厂的经济性。
When a large commercial reprocessing plant has not been built,the use of burnup credit(BUC)technology can realize the intensive storage of spent fuel,which is helpful to alleviate the operating pressure of nuclear power plants.Compared with the traditional new fuel assumption,BUC technology involves a wide variety of nuclides and the numerical calculation of burnup is complex.The actual burnup is difficult to fully consider the actual depletion process of components in the reactor,Moreover,due to the approximation introduced by depletion chain decomposition,the randomness of nuclear reaction itself and the inherent error of numerical calculation method,it is difficult to obtain accurate nuclear fuel composition in burnup calculation.Therefore,it is necessary to quantify the uncertainty introduced in the depletion calculation reasonably and conservatively.In order to quantify the critical safety uncertainty transmitted from burnup calculation in the application of BUC,based on the parameter statistical method,7 benchmark data of PWR chemical analysis published by ORNL and OCRWM,56 groups of spent fuel PWR components,with enrichment coverage of 2.56%-4.11%and burnup coverage of 11.5-47.3 GW·d/tU were selected.The experimental measured values of spent fuel samples used as the benchmark to compare with the calculated values of nuclides,the nuclide bias and bias uncertainty of burnup calculation were analyzed.Then,nuclide boundary method,Monte Carlo sampling and Latin hypercube sampling were used to modify nuclide.At the same time,the corrected nuclides were combined into different spent fuel assembly components.TRITON and CSAS25 modules were used with ENDF/B-Ⅴnuclear database for burnup calculation and criticality calculation respectively.The critical calculation results took the k_(inf) uncertainty calculated by Monte Carlo sampling method as a reference.Subsequently,the effects of nuclide boundary method,Monte Carlo sampling and Latin hypercube sampling method on the critical calculation uncertainty were compare
作者
倪梓宁
于涛
谢金森
陈熙荣
黄干
黄浩
陈珍平
赵鹏程
雷济充
NI Zining;YU Tao;XIE Jinsen;CHEN Xirong;HUANG Gan;HUANG Hao;CHEN Zhenping;ZHAO Pengcheng;LEI Jichong(School of Nuclear Science and Technology,University of South China,Hengyang 421001,China;Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology,University of South China,Hengyang 421001,China;Nuclear Reactor Operation and Application Research Sub-Institute,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2022年第9期1915-1923,共9页
Atomic Energy Science and Technology
基金
国家自然科学基金(11875162)
湖南省研究生科研创新项目(CX20190720)。
