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NEUTRON SHIELD ANALYSIS AND DESIGN FOR THE PDX FUSION FACILITY.
R. A. Grimesey
, D. W. Nigg
, A. J. Scott
, F. J. Wheeler
, D. L. Jassby
, E. D. Perry
, J. B. Frankenberg
Nuclear Reactor Technology
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Dive into the research topics of 'NEUTRON SHIELD ANALYSIS AND DESIGN FOR THE PDX FUSION FACILITY.'. Together they form a unique fingerprint.
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Keyphrases
Divertor
100%
Fusion Facility
100%
Neutron Shield
100%
Biological Shield
50%
Control Room
50%
Skyshine Dose
50%
Site Boundary
50%
Thin-walled
25%
Tokamak
25%
Controlled Experiment
25%
Controlling Factors
25%
Gamma Rays
25%
Magnetic Fusion Device
25%
Neutron Field
25%
Shielding Wall
25%
Design Objectives
25%
Polyethylene Tank
25%
High Density Concrete
25%
Removability
25%
Engineering
Control Room
100%
Tokamak Device
50%
Gamma Ray
50%
Design Objective
50%
Material Science
Density
100%
Polyethylene
100%
Physics
Tokamak Device
100%
Gamma Radiation
100%
Agricultural and Biological Sciences
Tanks
100%