Benchmarking of Mechanical Test Facilities Related to ITER CICC Steel Jackets

Authors :: K. Hamada
Soo-Hyeon Park
M. C. Jewell
I. Pong
Stefano Sgobba
Robert Walsh
T. Boutboul
Arnaud Devred
Alexander Vostner
V. Tronza
A. Jung
S. Liu
Denis Bessette
Wu Yu
K.P. Weiss
Source :: IEEE Transactions on Applied Superconductivity. 23:9500705-9500705
Publication Year :: 2013
Publisher :: Institute of Electrical and Electronics Engineers (IEEE), 2013.
Abstract: 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 (