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Recovery of Damage Indued by Irradiation Reactor Pressure Vessel Steels

Recovery of Damage Indued by Irradiation Reactor Pressure Vessel Steels
辐照反应堆压力容器钢损伤的恢复
批准号:
15560725
负责人:
XU Qiu
金额:
$2.3万
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:
2003
资助国家:
日本
项目状态:
已结题
起止时间:
2003 至 2005

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中文摘要
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英文摘要
The main purpose of the present study was to investigate the mechanism of miorostructural evolution in dilute Fe-Cu alloys, the model alloys of the reactor pressure vessel steels, and the range of vary temperature under vary temperature irradiation.Before investigation of effect of vary temperature on the microstructural evolution, it is necessary to investigate the miorostructural evolution at constant temperature. Two Fe-Cu alloys, namely Fe-0.3Cu and Fe-0.6Cu, were tested in this study. The neutron irradiations were carried out at the Kyoto University Reactor at 573 K. The results indicate that there are three stages in the formation of Cu precipitates. First, the precipitates nucleate by vacancy migration. Second, microvoids form and grow at these precipitates sites, and then the aggregation of Cu atoms is promoted at these microvoids because the surface energy of Cu is lower than that of Fe. Third, the microvoids form and grow in the matrix without any connection with Cu precipita … More tes.Two types of vary temperature irradiations, 573 K/723 K and 573 K/673 K, were carried out to investigate the recovery behavior of defect clusters Fe-Cu alloys. Microvoids and interstitial clusters disappeared, and Cu precipitates grew under vary temperature irradiation. The disappearance of microvoids and interstitial clusters was more prominent in the irradiation than in the annealing at 723 K. The recovery of microvoids and interstitial clusters and the formation of Cu precipitates in the irradiation of 573 K/723 K were more prominent than those in the irradiation of 573 K/673 K. In addition, the irradiation dose at low temperature also influenced the microstructural evolution during subsequent irradiation at high temperature. The results suggest that the lower the irradiation dose at 573 K, the greater the extent recovery of defect clusters in Fe-Cu alloys during irradiation at 673 K. They also suggest that a higher irradiation dose is needed to recover the defect clusters formed at 573 K with low irradiation dose. Inversely, a lower irradiation dose is needed to recover the defect clusters formed at 573 K with high irradiation dose. Less
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Detection of Interstitials and Their Clusters by PAC and Positron Lifetime Measurements on Neutron Irradiated Ni-Hf Alloy.
通过中子辐照 Ni-Hf 合金的 PAC 和正电子寿命测量检测间隙原子及其团簇。
DOI: --
发表时间: 2004
期刊: Journal of Nuclear Materials 329-333
影响因子: --
作者: [H.Okazawa, T.Yoshiie, T.Ishizaki, K.Sato, Q.Xu, Y.Satoh, Y.Ohkubo, Y.Kawase]
通讯作者: Y.Kawase
Anisotropic Motion of Point Defects near Edge Dislocations
边缘位错附近点缺陷的各向异性运动
DOI: --
发表时间: 2004
期刊: Journal of Nuclear Materials 329-333
影响因子: --
作者: [K.Sato, T.Yoshiie, Q.Xuv]
通讯作者: Q.Xuv
Q.Xu, T.Yoshiie: "Recovery Behavior of Defect Clusters in Fe-Cu Alloy Irradiated with Neutrons at High Temperature"Materials Science Forum. 445-446. 216-218 (2004)
Q.Xu,T.Yoshiie:“高温中子辐照铁铜合金中缺陷团簇的恢复行为”材料科学论坛。
DOI: --
发表时间:
期刊:
影响因子: --
作者: []
通讯作者:
Anisotropic Motion of Point Defects near Edge Dislocations.
边缘位错附近点缺陷的各向异性运动。
DOI: --
发表时间: 2004
期刊: Journal of Nuclear Materials 329-333
影响因子: --
作者: [K.Sato, T.Yoshiie, Q.Xu]
通讯作者: Q.Xu
37
    Effects of Damage rate on formation of Nano-Precipitates In Reactor Pressure Vessel
    • 批准号:
      20560773
    • 项目类别:
      Grant-in-Aid for Scientific Research (C)
    • 资助金额:
      $3.0万
    • 财政年份:
      2008
    • 负责人:
      XU Qiu
    • 依托单位: