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

F. Malouch
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引用次数: 14

Abstract

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.
OSIRIS材料试验堆堆芯核加热评估计算方案的开发与实验验证
在材料测试堆中辐照材料样品的温度控制需要了解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,建立了一个中子-光子三维计算方案,以评估在OSIRIS MTR反应堆(CEA/Saclay中心)堆芯辐照的实验装置中的核加热。目的是获得一种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 (Saclay Center)开发的TRIPOLI-4三维连续能蒙特卡罗输运代码。在OSIRIS核心进行的核加热测量的基础上进行了实验验证。在概述了OSIRIS反应堆辐照实验装置的基础上,给出了计算方案和实验验证的初步结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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