Development of advanced materials for spallation neutron sources and radiation damage simulation based on multi-scale models
Development of advanced materials for spallation neutron sources and radiation damage simulation based on multi-scale models
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DOI：
10.1016/j.jnucmat.2011.11.023
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发表时间：
2012-12
影响因子：
3.1
通讯作者：
M. Kawai;H. Kurishita;H. Kokawa;Seiichi Watanabe;N. Sakaguchi;K. Kikuchi;S. Saito;T. Yoshiie;H. Iwase;T. Ito;S. Hashimoto;Y. Kaneko;M. Futakawa;S. Ishino
中科院分区：
文献类型：
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作者：
M. Kawai;H. Kurishita;H. Kokawa;Seiichi Watanabe;N. Sakaguchi;K. Kikuchi;S. Saito;T. Yoshiie;H. Iwase;T. Ito;S. Hashimoto;Y. Kaneko;M. Futakawa;S. Ishino
这份报告描述了JSPS赠款小组为散裂中子源开发先进材料和建立辐射损害模型的现状审查。其中一种先进材料是增韧细晶钨材料(W-TiC)，它的断裂韧性是普通钨的四倍，在再结晶状态下具有可观的RT塑性。另一种是经晶界工程(GBE)处理的抗晶间裂纹(IGC)奥氏体不锈钢。实验结果包括铅-铋共晶中的腐蚀、焊接腐蚀的止蚀、辐射损伤和蠕变断裂以及采用激光和退火法进行GBE的新技术。新技术似乎适用于大型或复杂形状的部件。建立了从入射粒子与介质核之间的核反应到辐射损伤引起的材料性质变化的一系列多尺度模型。对3GeV质子轰击3 mm厚的镍进行了样品计算。
This report describes the status review of the JSPS Grant Team to develop advanced materials for the spallation neutron sources and modeling of radiation damage. One of the advanced materials is a toughness enhanced, fine-grained tungsten material (W-TiC) having four-times larger fracture toughness than ordinary tungsten and appreciable RT ductility in the recrystallized state. The other is an intergranular crack (IGC)-resistant austenitic stainless steel which was processed by the grain-boundary engineering (GBE). The experimental results are devoted to corrosion in a lead–bismuth eutectic, arrest of corrosion of weld-decay, radiation damage and creep rupture as well as new technique of GBE using a laser and annealing procedure. New technique seems to be applicable to large or complicated-shaped components. A series of the multi-scale models is built up from nuclear reaction between incident particles and medium nuclei to material property change due to radiation damage. Sample calculation is made on 3mm-thick nickel bombarded by 3GeV protons.