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Stability evaluation of point defect clusters to estimate microstructural change during irradiation

Stability evaluation of point defect clusters to estimate microstructural change during irradiation
点缺陷簇的稳定性评估以估计辐照期间微观结构的变化
批准号:
20560622
负责人:
JITSUKAWA Shiro
金额:
$2.08万
依托单位:
依托单位国家:
日本
项目类别:
Grant-in-Aid for Scientific Research (C)
财政年份:
2008
资助国家:
日本
项目状态:
已结题
起止时间:
2008 至 2010

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中文摘要
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英文摘要
Capture radius of interstitial loops for point defect clusters have been evaluated by in situ ion-irradiation experiment and model calculation. Relatively large capture radius for clusters was obtained. Also, the minimum size for dislocation loop exhibiting strain field has been detected, The value is of about 1nm. By using minimum size of interstitial loops and using capture radius for clusters fate and the stability of point defect clusters has been evaluated. The results are useful to control irradiation damage.
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Irradiation effects on reduced activation ferritic/martensitic steels-tensile, impact, fatigue properties and moldeling
辐照对降低活化铁素体/马氏体钢的拉伸、冲击、疲劳性能和成型性能的影响
DOI: --
发表时间: 2009
期刊: Nuclear Fusion 49
影响因子: --
作者: [S.jitsukawa, K.Suzuki, N.Okubo, M.Ando, K.Shiba]
通讯作者: K.Shiba
Preliminary models on irradiation induced changes of microstructure and stress-strain relations to estimate mechanical response of austenitic and martensitic steel components
辐照引起的微观结构和应力-应变关系变化的初步模型,用于估计奥氏体和马氏体钢部件的机械响应
DOI: --
发表时间: 2011
期刊:
影响因子: --
作者: [S.Jitsukawa, Y.Abe, K.Suzuki, N.Okubo]
通讯作者: N.Okubo
Intensely irradiated steel components : Plastic and fracture properties, and a new concept of structural design criteria for assuring the structural integrity
强辐照钢部件:塑性和断裂性能,以及确保结构完整性的结构设计标准的新概念
DOI: --
发表时间: 2010
期刊: Nuclear Engineering and Design 240
影响因子: --
作者: [K.Suzuki, S.Jitsukawa, N.Okubo, F.Takada]
通讯作者: F.Takada
Irradiation effects on reduced activation ferritic/martensitic steels-Mechanical properties and modeling-
辐照对降低活化铁素体/马氏体钢的影响-机械性能和建模-
DOI: --
发表时间: 2008
期刊:
影响因子: --
作者: [Shiro Jitsukawa, et al.]
通讯作者: et al.
12
    Behavior of nuclear reactor materials at high damage levels investigated by ion-irradiation and point defect reaction models
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