Manufacturing Data Uncertainties Propagation Method in Burn-Up Problems

被引:2
作者
Frosio, Thomas [1 ]
Bonaccorsi, Thomas [1 ]
Blaise, Patrick [2 ]
机构
[1] French Atom Energy & Alternat Energies Commiss CE, DEN, CAD, Reactor Studies Dept,Reactor Phys & Fuel Cycle Di, F-13108 St Paul Les Durance, France
[2] French Atom Energy & Alternat Energies Commiss CE, DEN, CAD, Reactor Studies Dept,Expt Phys Div, F-13108 St Paul Les Durance, France
关键词
COVARIANCES;
D O I
10.1155/2017/7275346
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A nuclear data-based uncertainty propagation methodology is extended to enable propagation of manufacturing/technological data (TD) uncertainties in a burn-up calculation problem, taking into account correlation terms between Boltzmann and Bateman terms. The methodology is applied to reactivity and power distributions in a Material Testing Reactor benchmark. Due to the inherent statistical behavior of manufacturing tolerances, Monte Carlo sampling method is used for determining output perturbations on integral quantities. A global sensitivity analysis (GSA) is performed for each manufacturing parameter and allows identifying and ranking the influential parameters whose tolerances need to be better controlled. We show that the overall impact of some TD uncertainties, such as uranium enrichment, or fuel plate thickness, on the reactivity is negligible because the different core areas induce compensating effects on the global quantity. However, local quantities, such as power distributions, are strongly impacted by TD uncertainty propagations. For isotopic concentrations, no clear trends appear on the results.
引用
收藏
页数:10
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