材料科学
奥氏体不锈钢
热核聚变
奥氏体
焊接
核工程
导线
韧性
冶金
复合材料
腐蚀
工程类
微观结构
核物理学
等离子体
物理
作者
A. Vostner,Ian Pong,D. Bessette,A. Devred,S. Sgobba,A. Jung,K.P. Weiss,Matthew C. Jewell,S. Liu,Yu Wu,T. Boutboul,K. Hamada,Sung Man Park,V. Tronza,R. P. Walsh
标识
DOI:10.1109/tasc.2013.2243895
摘要
The International Thermonuclear Experimental Reactor (ITER) cable-in-conduit conductor used in the superconducting magnet system consists of a cable made of 300 to 1440 strands housed in a stainless steel tube (called as jacket or conduit). There are circular, square, as well as circle-in-square jackets, made of either a very low carbon AISI 316LN and AISI 316L grade stainless steels, or a high Mn austenitic stainless steel developed for ITER called JK2LB. Selected mechanical properties of the base material and weld joint were tested at room temperature and/or cryogenic temperatures (<; 7 K) at predefined mechanical deformation and heat treatment condition. The domestic agencies' reference laboratories and the ITER-IO appointed reference laboratories, CERN and Karlsruhe Institute of Technology performed mechanical tests such as tensile strength, fracture toughness, and fatigue crack growth rate. This paper will compare the test results (e.g., elongation to failure) from different laboratories, present the statistics, and identify any systematic differences.
科研通智能强力驱动
Strongly Powered by AbleSci AI