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Development of Advanced Steels for Irradiation Environment

Development of Advanced Steels for Irradiation Environment
辐照环境用先进钢材的开发
批准号:
09045042
负责人:
TAKAHASHI Heishichiro
金额:
$1.22万
依托单位:
依托单位国家:
日本
项目类别:
Grant-in-Aid for international Scientific Research
财政年份:
1997
资助国家:
日本
项目状态:
已结题
起止时间:
1997 至 1998

项目摘要

项目成果

TAKAHASHI Heishichiro的其他基金

相关文献

中文摘要
翻译
1. 316不锈钢经电子辐照后,层错位错环形核,最后在位错环内部形成空位型层错四面体。在电子/He双重辐照下,这些SFT充当了空穴成核的位置. Fe-(15-16)% Cr-16% Mn-O. 2% C-O. 2% N钢的室温屈服应力为400 MPa,延伸率为60%。这些高Mn钢在辐照下表现出优异的耐辐照性能.当含有W和V的Fe-Cr-Mn(W,V)钢经过辐照后,没有发现偏析,因此建议通过添加W和V来减缓偏析。4.含W和V的Fe-Cr-Mn合金在625 K时具有较高的抗辐照性能,但在较高温度下会有大量的小空洞形核.在Fe-Cr-Mn钢中,晶界偏析比含W钢大V.6.lt并且对于Fe-(13-16)Cr-(13-16)Mn钢,(6.5-24.5)锰-(0.02-0.2)C-0.2 N钢,(a)通过控制Cr、C、N的成分,即使对于较低Mn浓度的钢,也可以获得奥氏体的单相,(B)Fe-(15-16)wt% Cr-15.5wt % Mn-(0.02 - 0.2)wt% C-0.2wt %N钢在473- 673 K的辐照下具有优异的力学性能,(c)Fe-16 wt % Cr-15.5wt % Mn-O. 2 wt % C-O. 2 wt % N钢在473- 673 K的辐照下具有良好的抗空洞形成性能。
英文摘要
1. When 316 stainless steel was electron-irradiated, stacking fault dislocation loops were nucleated, and then finally stacking fault tetrahedra of vacancy type (SFT) were nucleated inside the loops. These SFTs acted as void nucleation sites under electron/He dual irradiation.2. Fe-(15-16)% Cr-16% Mn-O.2% C-O.2% N steels have yield stress of 400 MPa and the elongation of 60% at room temperature. These high Mn steels showed excellent irradiation-resistance under irradiation.3. When Fe-Cr-Mn(W,V) steels with W and V were irradiated, no segregation was recognized, and then it was suggested that by adding W, and V segregation is retarded.4. The same Fe-Cr-Mn containing W and V showed higher resistance for irradiation at625K but at higher temperature a lot of small voids were nucleated.5. In Fe-Cr-Mn steels the segregation at grain boundary was larger than the steel with W and V.6.lt was clarified for Fe-(13-16) Cr-(6.5-24.5) Mn-(0.02-0.2)C-0.2 N steels that (a) by contorolling the composition of Cr, C,N single phase of austenite can be obtained even for lower Mn concentration steels, (b)Fe-(15-16)wt% Cr-15.5wt% Mn-(O.02-O.2)wt% C-0.2wt% N steels have excellent mechanical properties, and (c) voids formation were perfectly retarded for Fe-l6wt% Cr-15.5wt% Mn-O.2wt% C-O.2wt% N steel under irradiation at 473-673K.
期刊论文(23)
专著(0)
科研奖励(0)
会议论文
胡本芙: "Irradiation Damage of oxide Dispersion Strengthened Ferritic Steel after Recrystallizatioin" Jouranl of University of Science & Technology Beijing. 5. 160-164 (1998)
胡本富:“氧化物弥散强化铁素体钢再结晶后的辐照损伤”,北京科技大学学报,5. 160-164 (1998)。
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通讯作者:
高橋 平七郎: "Mechanical Properties and Damage Behaviors of Nonmagnetic High Manganese Austenitic Steel" J.Nuclear Matterials. (予定). (1998)
Heishichiro Takahashi:“非磁性高锰奥氏体钢的机械性能和损伤行为”J.Nuclear Matterials(计划)。
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N.Sakaguchi: "Effect of Additional Minor Element on Radiation -Induced Segregation in Austenitic Stanless Steel" Proc.of The 1998 Inter.Symp.on Advanced Energy Tech.639-642 (1998)
N.Sakaguchi:“附加微量元素对奥氏体不锈钢辐射诱导偏析的影响”Proc.of The 1998 Inter.Symp.on Advanced Energy Tech.639-642 (1998)
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斉藤 順: "Mechanical properties and damage behavior of non-magnetic high manganese austenitic steels." Journal Nuclear Materials. 258/263. 1644-1650 (1998)
Jun Saito:“非磁性高锰奥氏体钢的机械性能和损伤行为。”核材料杂志 258/263(1998)。
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共 22 条
    Study of Low Activation Materials for Fusion Reactor
    • 批准号:
      05044071
    • 项目类别:
      Grant-in-Aid for international Scientific Research
    • 资助金额:
      $3.84万
    • 财政年份:
      1993
    • 负责人:
      TAKAHASHI Heishichiro
    • 依托单位: