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Development and Experimental Validation of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor

机译:OSIRIS材料测试反应堆堆芯核热评估计算方案的开发和实验验证

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摘要

The control of the temperature in material samples irradiated in a material testing reactor requires the knowledge of the nuclear heating caused by the energy deposition by neutrons and photons interacting in the irradiation device structures. Thus, a neutron-photonic three-dimensional calculation scheme has been developed to evaluate the nuclear heating in experimental devices irradiated in the core of the OSIRIS MTR reactor (CEA/ Saclay Center). The aim is to obtain a predictive tool for the nuclear heating estimation in irradiation devices. This calculation scheme is mainly based on the TRIPOLI-4 three-dimensional continuous-energy Monte Carlo transport code, developed by CEA (Saclay Center). An experimental validation has been carried out on the basis of nuclear heating measurements performed in the OSIRIS core. After an overview of the experimental devices irradiated in the OSIRIS reactor, we present the calculation scheme and the first results of the experimental validation.
机译:控制在材料测试反应器中辐照的材料样品中的温度需要了解由在辐照装置结构中相互作用的中子和光子的能量沉积引起的核加热。因此,开发了一种中子光子三维计算方案,以评估辐照在OSIRIS MTR反应堆堆芯(CEA /萨克雷中心)内的实验装置中的核加热。目的是获得用于辐照装置中核加热估计的预测工具。该计算方案主要基于CEA(萨克雷中心)开发的TRIPOLI-4三维连续能量蒙特卡洛运输代码。基于在OSIRIS堆芯中进行的核加热测量,已经进行了实验验证。在概述了OSIRIS反应堆中辐照的实验装置之后,我们介绍了计算方案和实验验证的第一批结果。

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