Mechanical properties of various kinds of irradiated austenitic stainless steels

被引:0
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作者
Kodama, M [1 ]
Suzuki, S [1 ]
Nakata, K [1 ]
Nishimura, S [1 ]
Fukuya, K [1 ]
Kato, T [1 ]
Tanaka, Y [1 ]
Shima, S [1 ]
机构
[1] Nippon Nucl Fuel Dev Co Ltd, Oarai, Ibaraki 31113, Japan
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中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Type 304, 304L, and 21 heats of Type 316 and 347 stainless steels with compositional changes in P, Si, N and Nb were:irradiated in a boiling water reactor to 1.7-2.2x10(25)n/m(2) (E>1MeV) and 3.3-4.0x10(25)n/m(2) (E>1MeV). Tensile tests in 561K air and Micro-Vickers hardness measurements on irradiated and unirradiated specimens were conducted. For alloys irradiated to 1.3-2.1x10(25)n/m(2) (E>1MeV),: the yield stress was dependent on the bulk impurity content. P and Nb enhanced hardening while N suppressed ductility loss in commercial purity 316L and 347L showed a similar tendency. Yield stress was well correlated to:hardness. At 3.2-4.4x10(25)n/m(2) (E>1MeV), all the alloys exhibited a yield drop and fractured without work-hardening and the yield stress was not dependent on the bulk impurity content. The effects on radiation hardening of P and N disappeared with increasing neutron fluence.
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页码:831 / 838
页数:4
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