• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>20th International Symposium on Effects of Radiation on Materials, Jun 6-8, 2000, Williamsburg, Virginia >The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials Selected for the Target and Blanket Components in the Accelerator Production of Tritium Project
【24h】

The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials Selected for the Target and Blanket Components in the Accelerator Production of Tritium Project

机译：高能质子和中子对of项目加速器生产中靶材和毛毯成分选择材料的拉伸性能的影响

获取原文
获取原文并翻译 | 示例
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

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 ~3He 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 properties of candidate APT materials, 316L and 304L stainless steel (annealed), modified (Mod) 9Cr-lMo steel, and Alloy 718 (precipitation hardened), was measured on tensile specimens irradiated in the Los Alamos Neutron Science Center accelerator, which operates at an energy of 800 MeV and a current of 1 mA. The irradiation temperatures ranged from 50-164℃, 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 10,000 appm H and 1,000 appm He for the Type 304L stainless steel tensile specimens. Specimens were tested at the irradiation temperature of 50-164℃. Less than 1 dpa of exposure reduced the uniform elongation of Alloy 718 (precipitation hardened) and mod 9Cr-1Mo to less than 2%. 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 1 dpa. These results are discussed and compared with results of similar materials irradiated in fission reactor environments.
机译：of的加速器生产（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〜3He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。在洛斯阿拉莫斯中子辐照的拉伸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）的拉伸性能的影响。科学中心加速器，其能量为800 MeV，电流为1 mA。辐照温度范围为50-164℃，这是APT目标/毯子所预期的典型温度。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，最大暴露量等于dpa为12，产生10,000 appm H和1,000 appm He。在50-164℃的照射温度下测试样品。小于1 dpa的暴露量会使718合金（沉淀硬化）和mod 9Cr-1Mo的均匀伸长率降低到2％以下。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。小于1 dpa后，奥氏体钢的屈服应力增加到其非辐照值的两倍以上。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。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号