k_(eff)uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor  被引量:4

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作  者:Rong-Rui Yang Yuan Yuan Chen Hao Ji Ma Guang-Hao Liu 

机构地区:[1]Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,College of Nuclear Science and Technology,Harbin Engineering University,Harbin 150001,China [2]Department of Reactor Technology,Beijing Institute of Nuclear Engineering,China Nuclear Power Engineering Co.,Ltd,Beijing 100089,China

出  处:《Nuclear Science and Techniques》2021年第11期105-118,共14页核技术(英文)

基  金:supported by the National Natural Science Foundation of China(No.12075067);the National Key R&D Program of China(No.2018YFE0180900)。

摘  要:To benefit from recent advances in modeling and computational algorithms,as well as the availability of new covariance data,sensitivity and uncertainty analyses are needed to quantify the impact of uncertain sources on the design parameters of small prismatic high-temperature gascooled reactors(HTGRs).In particular,the contribution of nuclear data to the k_(eff)uncertainty is an important part of the uncertainty analysis of small-sized HTGR physical calculations.In this study,a small-sized HTGR designed by China Nuclear Power Engineering Co.,Ltd.was selected for k_(eff)uncertainty analysis during full lifetime burnup calculations.Models of the cold zero power(CZP)condition and full lifetime burnup process were constructed using the Reactor Monte Carlo Code RMC for neutron transport calculation,depletion calculation,and sensitivity and uncertainty analysis.For the sensitivity analysis,the Contribution-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance Characterization(CLUTCH)method was applied to obtain sensitive information,and the "sandwich" method was used to quantify the k_(eff)uncertainty.We also compared the k_(eff)uncertainties to other typical reactors.Our results show that ^(235)U is the largest contributor to k_(eff)uncertainty for both the CZP and depletion conditions,while the contribution of ^(239)Pu is not very significant because of the design of low discharge burnup.It is worth noting that the radioactive capture reaction of ^(28)Si significantly contributes to the k_(eff)uncertainty owing to its specific fuel design.However,the k_(eff)uncertainty during the full lifetime depletion process was relatively stable,only increasing by 1.12%owing to the low discharge burnup design of small-sized HTGRs.These numerical results are beneficial for neutronics design and core parameters optimization in further uncertainty propagation and quantification study for small-sized HTGR.

关 键 词:Small-sized HTGR SU analysis Nuclear data BURNUP 

分 类 号:TL424[核科学技术—核技术及应用]

 

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