
Evaluation of a nonevaporable getter pump for tritium handling in the Tokamak Fusion Test Reactor
Author(s) -
M.F. Singleton,
C.M. Griffith
Publication year - 1978
Language(s) - English
Resource type - Reports
DOI - 10.2172/6411863
Subject(s) - tokamak fusion test reactor , getter , tokamak , nuclear engineering , cartridge , tritium , fusion power , materials science , nuclear physics , radiochemistry , chemistry , engineering , plasma , physics , metallurgy , optoelectronics