Development of Advanced Steels for Irradiation Environment
Grant-in-Aid for international Scientific Research
|Allocation Type||Single-year Grants |
|Section||University-to-University Cooperative Research|
Nuclear fusion studies
|Research Institution||HOKKAIDO UNIVERSITY |
TAKAHASHI Heishichiro Hokkaido University, Center for Advanced Research of Energy Technology, Professor, エネルギー先端工学研究センター, 教授 (80001337)
万 発栄 北京科技大学材料系, 教授
胡 本芙 北京科技大学材料系, 教授
KINOSHITA Hiroshi Hokkaido Univ.Center for Advanced Res.of Energy Tech.Assistant, エネルギー先端工学研究センター, 助手 (40177895)
SHIBAYAMA Tamaki Hokkaido Univ.Center for Advanced Res.of Energy Tech.Assistant, エネルギー先端工学研究センター, 助手 (10241564)
HU Benfu University of Science & Tech.Beijing, Dep.of Maters., Professor
WAN Farong University of Science & Tech.Beijing, Dep.of Maters., Professor
渡辺 精一 北海道大学, 大学院・工学研究科, 助教授 (60241353)
|Project Period (FY)
1997 – 1998
Completed (Fiscal Year 1998)
|Budget Amount *help
¥1,900,000 (Direct Cost: ¥1,900,000)
Fiscal Year 1998: ¥900,000 (Direct Cost: ¥900,000)
Fiscal Year 1997: ¥1,000,000 (Direct Cost: ¥1,000,000)
|Keywords||high Mn steel / lower radioactivity / fusion reactor / electron-irradiation / radiation-damage / He effect / mechanical properties / void swelling / 相不安定性 / ボイドフェリング|
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 at
625K 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.
Report (3 results)
Research Products (23 results)