Re-evaluation of neutron displacement cross sections for silicon carbide by a Monte Carlo approach

Re-evaluation of neutron displacement cross sections for silicon carbide by a Monte Carlo approach
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用蒙特卡罗方法重新评估碳化硅的中子位移截面

DOI:
10.1080/00223131.2015.1028502
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发表时间:
2016-02
影响因子:
1.2
通讯作者:
曹兴庆
曹兴庆
中科院分区:
工程技术4区
文献类型:
--
作者:
郭达禧;贺朝会;臧航;张鹏;马梨;李涛;曹兴庆

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SIC的中子位移横截面通过Monte Carlo方法重新评估,并具有损坏。通过物质(SRIM)代码的离子范围和离子范围计算出的主要后坐力的能量。蒙特卡洛模型的有效性是由铁的情况检查的,结果与参考值表示很好。计算了高达100 MeV的SIC的中子位移横截面,并在融合量反应器的中子光谱上进行了空调,国际材料辐射设施的高通量测试模块,典型的裂变测试反应堆。GAS的产生。计算出来的中子辐射设施。最后,讨论了位移横截面的适用性。通过当前的位移对不同设施的中子辐照之间的比较结果。杂交部分与先前工作的结果相似。此外,由于中子位移。本研究中的跨部分是用SRIM计算出的主要后坐力的损伤能量计算的,因此由我们的位移横截面评估的中子损伤适合与由SRIM计算出的损害的损伤相关。
Neutron displacement cross sections for SiC are re-evaluated by a Monte Carlo approach, with damage.energies of primary recoils calculated by the stopping and range of ions in matter (SRIM) code. The validity.of the Monte Carlo model is examined by the case of iron, and the results show good agreement with the.reference values. Neutron displacement cross sections for SiC at energies up to 100 MeV are calculated, and.averaged over the neutron spectra of a fusionDEMOreactor, the high flux test module of the International.Fusion Materials Irradiation Facility, and typical fission test reactors.Gas production is also calculated for.those neutron irradiation facilities. Finally, the suitability of the displacement cross sections is discussed..The results on comparison among neutron irradiation of different facilities by the current displacement.cross sections are similar to those by results of the previous work. Moreover, since neutron displacement.cross sections in this study are calculated with damage energies of primary recoils calculated by SRIM,.neutron damage evaluated by our displacement cross sections is suitable for correlation with damage by.heavy ions calculated by SRIM.
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