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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250-450 degrees C
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Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250-450 degrees C

机译：在250-450摄氏度范围内的中子辐照后还原活化和常规马氏体钢的力学行为

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摘要

The objective of this work is to examine the susceptibility to hardening and embrittlement of Fe7.5/11CrWTaV reduced-activation (RA) and conventional 9/12Cr-Mo martensitic steels as a function of fluence up to 10 dpa and irradiation temperature in the range of 250-450 degreesC. For this purpose, materials were irradiated in the Osiris Reactor (Saclay) at 325 degreesC for Various doses ranging from 0.8 dpa to a maximum dose of 8-9 dpa. Available data concern the evolution of tensile properties for doses from 0.8 to 3.4 dpa. On the other hand, RA-steels were irradiated as Charpy V and tensile specimens in the high flux reactor (HFR) at Petten at temperatures ranging from 250 degreesC to 450 degreesC with a dose of about 2.4 dpa. (C) 2000 Elsevier Science B.V. All rights reserved. [References: 11]
机译：这项工作的目的是研究Fe7.5 / 11CrWTaV还原活化（RA）和常规9 / 12Cr-Mo马氏体钢对硬化和脆化的敏感性，其通量高达10 dpa，辐照温度范围为250-450℃。为此，将材料在Osiris反应器（Saclay）中于325℃下辐照0.8 dpa至最大8-9 dpa的各种剂量。现有数据涉及从0.8到3.4 dpa剂量的拉伸性能的演变。另一方面，在佩滕的高通量反应器（HFR）中以250摄氏度至450摄氏度的温度以约2.4 dpa的剂量将RA钢作为夏比V和拉伸试样进行辐照。 （C）2000 Elsevier Science B.V.保留所有权利。 [参考：11]

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