首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >The mechanical properties of 316L/304L stainless steels, Alloy 718 and Mod 9Cr-1Mo after irradiation in a spallation environment
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The mechanical properties of 316L/304L stainless steels, Alloy 718 and Mod 9Cr-1Mo after irradiation in a spallation environment

机译:316L / 304L不锈钢,718合金和Mod 9Cr-1Mo在散裂环境中辐照后的机械性能

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The Accelerator Production of Tritium (APT) project proposes to use a 1.0 GeV, 100 mA proton beam to produce neutrons via spallation reactions in a tungsten target. The neutrons are multiplied and moderated in a lead/aluminum/water blanket and then captured in He-3 to form tritium. The materials in the target and blanket region are exposed to protons and neutrons with energies into the GeV range. The effect of irradiation on the tensile and fracture toughness properties of candidate APT materials, 316L and 304L stainless steel (annealed), modified (Mod) 9Cr-1Mo steel, and Alloy 718 (precipitation hardened), was measured on tensile and fracture toughness specimens irradiated at the Los Alamos Neutron Science Center accelerator, which operates at an energy of 800 MeV and a current of I mA. The irradiation temperatures ranged from 50 degreesC to 164 degreesC, prototypic of those expected in the APT target/blanket. The maximum achieved proton fluence was 4.5 x 10(21) p/cm(2) for the materials in the center of the beam. This maximum exposure translates to a dpa of 12 and the generation of 10000 appm H and 1000 appm He for the Type 304L stainless steel tensile specimens. Specimens were tested at the irradiation temperature of 50-164 degreesC. Less than I dpa of exposure reduced the uniform elongation of the Alloy 718 (precipitation hardened) and Mod 9Cr-1Mo to less than 2%. This same dose reduced the fracture toughness by 50%. Approximately 4 dpa of exposure was required to reduce the uniform elongation of the austenitic stainless steels (304L and 316L) to less than 2%. The yield stress of the austenitic steels increased to more than twice its non-irradiated value after less than I dpa. The fracture toughness reduced significantly by 4 dpa to similar to 100 MPa m(1/2). These results are discussed and compared with results of similar materials irradiated in fission reactor environments. (C) 2001 Elsevier Science B.V. All rights reserved. [References: 13]
机译:of加速器生产(APT)项目建议使用1.0 GeV,100 mA质子束通过钨靶中的散裂反应产生中子。中子在铅/铝/水毯中繁殖并缓和,然后在He-3中捕获形成form。目标和覆盖区域中的材料暴露于质子和中子,能量在GeV范围内。在拉伸和断裂韧性试样上测量了辐照对候选APT材料,316L和304L不锈钢(退火),改性(改良)9Cr-1Mo钢和718合金(沉淀硬化)的拉伸和断裂韧性性能的影响。辐射在洛斯阿拉莫斯中子科学中心加速器上进行,加速器的能量为800 MeV,电流为I mA。辐照温度范围为50摄氏度至164摄氏度,这是APT目标/毯子所预期的原型温度。对于束中心的材料,最大质子通量为4.5 x 10(21)p / cm(2)。对于304L型不锈钢拉伸试样,最大暴露量可将dpa转换为12,并产生10000 appm H和1000 appm He。在50-164℃的照射温度下测试样品。小于I dpa的暴露会使718合金(沉淀硬化)和Mod 9Cr-1Mo的均匀伸长率降低到2%以下。相同剂量会使断裂韧性降低50%。为了使奥氏体不锈钢(304L和316L)的均匀伸长率降低到2%以下,需要大约4 dpa的暴露量。在小于I dpa之后,奥氏体钢的屈服应力增加到其非辐照值的两倍以上。断裂韧性降低了4 dpa,与100 MPa m(1/2)相似。对这些结果进行了讨论,并与在裂变反应堆环境中辐照的类似材料的结果进行了比较。 (C)2001 Elsevier Science B.V.保留所有权利。 [参考:13]

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