At the Lawrence Livermore and Berkeley Laboratories two major neutral beam system designs were developed, the High Voltage Test Stand (HVTS) and a conceptual system for the Two Component Tokamak-Toroidal Fusion Test Reactor (TCT- TFTR). The HVTS was designed for flexibility in performing a wide variety of tests, while the TCT-TFTR beam line was designed to satisfy particular requirements for target-plasma operation. Both designs make use of condensation cryopumping to handle very high gas loads. The HVTS design involves high-voltage isolation techniques of cryogenic and other systems. The TCT-TFTR design requires optimization of pumping and other systems. It is to be expected that experience gained from design and operation of the HVTS syst...
Design of the TFTR poses special engineering problems as a result of constraints posed by the physic...
A conceptual design has been developed for a moderate size (R = 6.0 m) high field (B = 13.1 T at the...
Neutral beam injectors and divertors for fusion devices require very high-speed pumping capabilities...
The neutral-beam injection requirements for heating and fueling the next generation of fusion reacto...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
This paper describes the present design and future capability of the high-voltage test stand for neu...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
The next generation of CTR experiments, such as the Tokamak Fusion Test Reactor (TFTR), will require...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be e...
We have attempted to make detailed designs of several neutral beam systems which would be applicable...
The cryocondensation pumping system for the TFTR neutral beam injectors is described. Topics include...
The main purpose of the Divertor Tokamak Test facility (DTT) [1], whose construction is starting in ...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
The Lawrence Berkeley and Livermore Laboratories Neutral Beam Development Group's work proceeds alon...
Design of the TFTR poses special engineering problems as a result of constraints posed by the physic...
A conceptual design has been developed for a moderate size (R = 6.0 m) high field (B = 13.1 T at the...
Neutral beam injectors and divertors for fusion devices require very high-speed pumping capabilities...
The neutral-beam injection requirements for heating and fueling the next generation of fusion reacto...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
This paper describes the present design and future capability of the high-voltage test stand for neu...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
The next generation of CTR experiments, such as the Tokamak Fusion Test Reactor (TFTR), will require...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be e...
We have attempted to make detailed designs of several neutral beam systems which would be applicable...
The cryocondensation pumping system for the TFTR neutral beam injectors is described. Topics include...
The main purpose of the Divertor Tokamak Test facility (DTT) [1], whose construction is starting in ...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
The Lawrence Berkeley and Livermore Laboratories Neutral Beam Development Group's work proceeds alon...
Design of the TFTR poses special engineering problems as a result of constraints posed by the physic...
A conceptual design has been developed for a moderate size (R = 6.0 m) high field (B = 13.1 T at the...
Neutral beam injectors and divertors for fusion devices require very high-speed pumping capabilities...