首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel
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Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel

机译:裂变中子和质子/剥落中子辐照对316和304型不锈钢拉伸行为的影响比较

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摘要

As part of the accelerator production of tritium and the spallation neutron source programs, the tensile properties of annealed 304L 316LN and 316L stainless steel have been measured after proton and spallation neutron irradiation in the target region of the Los Alamos Neutron Science Center (LANSCE) accelerator (800 MeV, 1 mA) to a maximum dose of 12 dpa at temperatures ranging from 30 to 120degreesC. In addition to the displacement damage produced from the irradiation, up to several thousand atomic parts per million (appm) of hydrogen and helium were produced in the irradiated material via spallation reactions. Results of tensile tests at temperatures from room temperature up to 164degreesC show large increases in tensile yield strength, small increases in ultimate tensile strength, reductions in strain hardening capacity and reductions in ductility (uniform elongation and strain-to-necking) with increasing irradiation dose. A comparison of these data with the large database on tensile properties of type 316 stainless steel exposed to fission neutrons and tensile tested over the same temperature range show similar trends with regard to strength changes, but significantly larger reductions in ductility with irradiation dose were observed after irradiation in the spallation environment. The much higher amounts of helium and hydrogen produced through spallation in the LANSCE spectrum, compared to those developed in fission neutron irradiation environments at equivalent doses, may contribute to degradation in ductility. (C) 2003 Elsevier Science B.V. All rights reserved. [References: 22]
机译:作为the加速器生产和散裂中子源程序的一部分,在洛斯阿拉莫斯中子科学中心(LANSCE)加速器的目标区域内,质子和散裂中子辐照后,测量了退火的304L 316LN和316L不锈钢的拉伸性能(800 MeV,1 mA)在30至120摄氏度的温度下最大剂量为12 dpa。除了由于辐照产生的位移破坏外,通过散裂反应在辐照的材料中还产生了百万分之几千的氢和氦原子。从室温到164摄氏度的温度下的拉伸试验结果表明,随着辐照剂量的增加,抗拉屈服强度大幅度提高,极限抗拉强度小幅度提高,应变硬化能力降低,延展性降低(均匀伸长率和应变至颈缩) 。将这些数据与暴露于裂变中子的316不锈钢类型的大型拉伸性能数据库进行了比较,并在相同温度范围内进行了拉伸测试,结果表明强度变化趋势相似,但观察到随着辐照剂量的增加,延展性明显降低剥落环境中的辐射。与在裂变中子辐照环境中以等剂量产生的氦和氢相比,在裂隙中子辐照环境中通过散裂产生的大量氦和氢可能会导致延展性下降。 (C)2003 Elsevier Science B.V.保留所有权利。 [参考:22]

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