Evaluation of a Nonevaporable Getter Pump for Tritium Handling in the Tokamak Fusion Test Reactor.

摘要

Lawrence Livermore Laboratory has tested and evaluated a commercially available getter pump for use with tritium in the Tokamak Fusion Test Reactor (TFTR). The pump contains Zr(84%)--Al in cartridge form with a concentric heating unit. It performed well in all tests,except for frequent heater failures. (ERA citation 04:025086)