Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)
Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)
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DOI：
10.1016/j.fusengdes.2010.12.041
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发表时间：
2011-10
影响因子：
1.7
通讯作者：
F. Mota;R. Vila;C. Ortiz;A. García;N. Casal;Á. Ibarra;D. Rapisarda;V. Queral
中科院分区：
文献类型：
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作者：
F. Mota;R. Vila;C. Ortiz;A. García;N. Casal;Á. Ibarra;D. Rapisarda;V. Queral
目前通往聚变反应堆的途径包括严格的材料测试计划。为了达到这一目标，辐照设施必须产生尽可能接近未来聚变堆预期的每原子位移损伤（dpa）、初级撞击原子（PKA）谱和嬗变反应气态元素（He、H）（如DEMO）。聚变堆候选材料的PKA谱和损伤函数（Al2O3，SiC和Fe）进行了研究，然后，一些拟议的实验设施，如IFMIF和TechnoFusion，以下方法已被应用：IFMIF的不同辐照模块中存在的中子通量已被计算的中子输运McDeLicious代码。同时，用NJOY程序计算了PKA的能量微分截面。在此之后，使用MARLOWE代码（二进制碰撞近似）和自定义分析代码分析PKA谱产生的损伤。最后，利用SRIM程序和Marlowe程序分析了TechnoFusion辐照区不同辐照条件下的离子效应。结果已与预期的DEMO HCLL反应堆。
Present pathway to fusion reactors includes a rigorous material testing program. To reach this objective, irradiation facilities must produce the displacement damage per atom (dpa), primary knock-on atom (PKA) spectrum and gaseous elements by transmutation reactions (He, H) as closely as possible to the ones expected in the future fusion reactors (as DEMO).The irradiation parameters (PKA spectra and damage function) of some candidate materials for fusion reactors (Al2O3, SiC and Fe) have been studied and then, the suitability of some proposed experimental facilities, such as IFMIF and TechnoFusion, to perform relevant tests with these materials has been assessed.The following method has been applied: neutron fluxes present in different irradiation modules of IFMIF have been calculated by the neutron transport McDeLicious code. In parallel, the energy differential cross sections of PKA have been calculated by using the NJOY code. After that, the damage generated by the PKA spectra was analyzed using the MARLOWE code (binary collision approximation) and custom analysis codes. Finally, to analyze the ions effects in different irradiation conditions in the TechnoFusion irradiation area, the SRIM and Marlowe codes have been used. The results have been compared with the expected ones for a DEMO HCLL reactor.