首页> 美国政府科技报告 >Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steelsand Alloy 718 After Irradiation in High-Energy, Mixed Proton/Neutron Spectrum
【24h】

Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steelsand Alloy 718 After Irradiation in High-Energy, Mixed Proton/Neutron Spectrum

机译:304L和316L奥氏体不锈钢及718合金在高能混合质子/中子能谱辐照后的断裂韧性表征

获取原文

摘要

This paper describes the fracture toughness characterization of annealed 304L and316L stainless steels and precipitation hardened Alloy 718, performed at the Oak Ridge National Laboratory as a part of the experimental design and development for the Accelerator Production of Tritium (APT) target/blanket system. Materials were irradiated at 25 to 200 degrees Centrigrade(C) by high-energy protons and neutrons from an 800-MeV, 1-mA proton beam at the Los Alamos Neutron Science Center (LANSCE). The proton flux produced in LANSCE is nearly prototypic of anticipated conditions for significant portions of the APT target/blanket system. The objective of this testing program was to determine the change in crack-extension resistance of candidate APT materials from irradiation at prototypic APT temperatures and proton and neutron fluxes. J-integral-resistance (J-R) curve toughness tests were conducted in general accordance with the American Society for Testing and Materials Standard Test Method for Measurement of Fracture Toughness, E 1820-99, with a computer-controlled test and data acquisition system.

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