11 research outputs found
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Cryopumping system for TFTR neutral beam injectors
The cryocondensation pumping system for the TFTR neutral beam injectors is described. Topics include hardware design, differential pumping and beam loss, operational modes, and response to massive vacuum breaks
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MFTF vacuum vessel and cryopumping system
The Mirror Fusion Test Facility (MFTF) vacuum vessel and cryopumping system have attracted considerable interest within the fusion research community. Their extreme size, coupled with severe performance requirements and unique design features, justifies this interest. The planned expansion of the system to a tandem mirror configuration with thermal barriers further increases the engineering challenges of this complex facility
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Alternatives for contaminant control during MFTF plasma buildup
The MFTF mirror device considers all low-energy species to be contaminants, since their primary effect is to erode the plasma boundary by charge-exchange reactions. Confinement for other than hydrogen isotypes is far from complete and confinement time is hardly more than transit time from the source to the end wall. The brevity of the confinement time makes it all the more necessary to prevent any contamination which might further reduce it. At Livermore, the historical solution to contaminant control has been to evaporate titanium onto cold surfaces. An alternative to this approach and its implications are considered. (MOW
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NUCLEAR EXCITATION OF Al, Si, Ca AND Co PRODUCED BY u- CAPTURE
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DOPPLER BROADENING OF THE 6.322-MeV >--RAY FROM 15N FOLLOWING h' CAPTURE IN l6O
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DOPPLER BROADENING OF THE 6.322-MeV >--RAY FROM 15N FOLLOWING h' CAPTURE IN l6O
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PARTIAL CAPTURE RATES OF MUONS BY l6O LEADING TO EXCITED NUCLEAR STATES OF 15N
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Neutral beam injection system for the Tokamak Fusion Test Reactor
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facility. This is a major step to reach the goal of fusion power using toroidal magnetic fields for plasma confinement. A major part of this test reactor will be four neutral beam injection systems. These systems will inject 20 MW of 120 kV neutral deuterium atoms into the plasma for 0.5 seconds. In order to achieve the required power input to the plasma, several systems are required within the neutral beam line. These are the source, neutralizer, ion deflection magnet, calorimeter and retraction system, ion dump, cryopumps and vacuum enclosure. All of these systems have constraints imposed which increase the complexity of their designs. Since all systems must operate in a tritium environment, remote handling capabilities must be incorporated into the design. An overview is presented of the Lawrence Livermore Laboratory/Lawrence Berkeley Laboratory Neutral Beam Injection System design. Specifications for the machine and a general description of the total system are presented
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Final design of the neutral beam lines for the Tokamak Fusion Test Reactor
Final design of the neutral beam lines for TFTR has been completed. A prototype has been assembled at Lawrence Berkeley Laboratory and is undergoing testing as part of the Neutral Beam System Test Facility (NBSTF). The final neutral beam line (NBL) configuration differs in several details from that previously reported upon; certain components have been added; and testing of the cryopump system has led to some design simplification. It is these developments which are reported herein