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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Tensile properties and fracture mode of a wrought ODS molybdenum sheet following fast neutron irradiation at temperatures ranging from 300 degrees C to 1000 degrees C
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Tensile properties and fracture mode of a wrought ODS molybdenum sheet following fast neutron irradiation at temperatures ranging from 300 degrees C to 1000 degrees C

机译:在300到1000摄氏度的温度下快速中子辐照后,变形的ODS钼片材的拉伸性能和断裂模式

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摘要

A commercially available wrought oxide dispersion strengthened (ODS) molybdenum alloy was irradiated in the high flux isotope reactor (HFIR) at 294-936 degrees C to neutron fluences between 2.28 and 24.7 x 10(25) n/m(2) (E > 0.1 MeV) or (1.2-13.1 dpa-Mo). Irradiation of ODS molybdenum at 300 degrees C and 600 degrees C results in large increases in strength (57-173%). The DBTT for 300 degrees C-irradiated ODS Mo was 800 degrees C, which is the same as observed for low carbon are cast (LCAC) and TZM molybdenum irradiated to the same dose. The DBTT for 600 degrees C-irradiated ODS Mo was room-temperature, which is a significant improvement over the DBTT values determined for LCAC (300 degrees C) and TZM (700 degrees C) and from literature data. The micro-structural feature of small, elongated grains likely enhances the resistance of ODS to irradiation embrittlement. Irradiation of ODS Mo at 870-1000 degrees C resulted in small increases in yield strength (10-34%) with a post-irradiated DBTT comparable to non-irradiated material (-100 degrees C). (c) 2005 Elsevier B.V. All rights reserved.
机译:在294-936摄氏度下于高通量同位素反应堆(HFIR)中辐照可商购的可锻氧化物弥散强化(ODS)钼合金,使中子注量在2.28至24.7 x 10(25)n / m(2)之间(E> 0.1 MeV)或(1.2-13.1 dpa-Mo)。在300摄氏度和600摄氏度下辐照ODS钼会导致强度大幅提高(57-173%)。 300摄氏度辐照的ODS Mo的DBTT为800摄氏度,与低碳铸件(LCAC)和TZM钼辐照的剂量相同。 600摄氏度辐照的ODS Mo的DBTT是室温,这是对LCAC(300摄氏度)和TZM(700摄氏度)以及从文献数据确定的DBTT值的重大改进。小而细长的晶粒的微观结构特征可能会增强ODS对辐照脆化的抵抗力。在870-1000摄氏度下对ODS Mo进行辐照后,与未经辐照的材料(-100摄氏度)相比,辐照后的DBTT导致屈服强度小幅增加(10-34%)。 (c)2005 Elsevier B.V.保留所有权利。

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