Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor—II: Burnup Calculations
Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor—II: Burnup Calculations
复制标题
通过研究在敦雷原型快堆中辐照 492 天的样品来验证次锕系元素横截面 - II：燃耗计算
DOI：
10.13182/nse03-a2348
复制
发表时间：
2003
影响因子：
1.2
通讯作者：
S. Raman
中科院分区：
文献类型：
--
作者：
K. Tsujimoto;N. Kohno;N. Shinohara;T. Sakurai;Y. Nakahara;T. Mukaiyama;S. Raman
摘要为了评价次锕系元素（MAs）的中子截面数据，分离的锕系元素样品和剂量学样品在Dounreay原型快堆中辐照了492个有效全功率日。辐照样品在橡树岭国家实验室和日本原子能研究所（JAERI）进行了分析。这种独立的复制导致产生可靠的放射化学分析数据。根据主要锕系元素（235 U和239 Pu）和剂量学样品的燃耗计算，调整了MA样品辐照位置的中子通量分布和通量水平。使用确定的通量分布和通量水平进行的燃耗计算MA。计算结果与实验数据进行了比较。一个简单的说明样品制备和照射和详细的讨论，在JAERI的放射化学分析给出了一个配套文件。本文讨论了燃耗计算和验证评估核数据库中的MA截面数据。
Abstract To evaluate neutron cross-section data of minor actinides (MAs), separated actinide samples and dosimetry samples were irradiated at the Dounreay Prototype Fast Reactor for 492 effective full-power days. Irradiated samples were analyzed both at Oak Ridge National Laboratory and at Japan Atomic Energy Research Institute (JAERI). This independent duplication has resulted in the generation of reliable radiochemical analysis data. Based on the burnup calculations of major actinide (235U and 239Pu) and dosimetry samples, the neutron flux distribution and the flux level were adjusted at the locations where MA samples were irradiated. The burnup calculations were carried out for MAs using the determined flux distribution and flux level. The calculated results were compared with the experimental data. A brief description of sample preparation and irradiation and a detailed discussion of radiochemical analysis at JAERI are given in a companion paper. The current paper discusses the burnup calculations and the validation of MA cross-section data in evaluated nuclear data libraries.