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Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

机译:核衰变数据对乏燃料池热负荷估算不确定性的贡献研究

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摘要

At the Paul Scherrer Institut (PSI), a methodology for nuclear data uncertainty propagation in CASMO-5M (C5M) assembly calculations is under development. This paper presents a preliminary application of this methodology to C5M decay heat calculations. Applying a stochastic sampling method, nuclear decay data uncertainties are first propagated for the cooling phase only. Thereafter, the uncertainty propagation is enlarged to gradually account for cross-section as well as fission yield uncertainties during the depletion phase. On that basis, assembly heat load uncertainties as well as total uncertainty for the entire pool are quantified for cooling times up to one year. The relative contributions from the various types of nuclear data uncertainties are in this context also estimated.
机译:在Paul Scherrer研究所(PSI),正在开发一种在CASMO-5M(C5M)组装计算中传播核数据不确定性的方法。本文介绍了该方法在C5M衰减热计算中的初步应用。应用随机抽样方法,首先仅在冷却阶段传播核衰变数据的不确定性。此后,不确定度的传播扩大,以逐渐解释在枯竭阶段的横截面以及裂变产量的不确定性。在此基础上,可以对最多一年的冷却时间对装配热负荷的不确定性以及整个池的总不确定性进行量化。在这种情况下,还估算了各种类型核数据不确定性的相对贡献。

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  • 来源
    《Nuclear Data Sheets》 |2014年第4期|498-501|共4页
  • 作者单位

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland;

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland;

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland;

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland;

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland;

    Paul Scherrer Institut, CH-5232-Villigen PSI, Switzerland,Ecole Polytechnique Federale de Lausanne, CH-1015 Lausanne, Switzerland;

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