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Radiochemical Facilities for the Molten Salts in Nuclear Technologies Network (NNUF)
Sharrad, Clint
(PI)
Abram, Timothy
(CoI)
Burke, Grace
(CoI)
Connolly, Brian
(CoI)
Holmes, Stuart
(CoI)
Jones, Abbie
(CoI)
Turner, Joel
(CoI)
Grebennikova, Tatiana
(Grant contributor)
Department of Chemical Engineering
Department of Materials
CE - Academic & Research
Overview
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Research output
(1)
Activities
(1)
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Explore the research topics touched on by this project. These labels are generated based on the underlying awards/grants. Together they form a unique fingerprint.
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Engineering
Spent Nuclear Fuel
100%
Molten Salt Reactor
83%
Reactor Design
66%
Key Process
41%
Melting Point
41%
Underpinnings
41%
Liquid Phase
41%
Nuclear Fuel Cycle
16%
Crossover
16%
Nuclear Power Plant
16%
Safety Case
16%
Nuclear Reactor
16%
Case Basis
16%
Advanced Nuclear Reactor
16%
Larger Quantity
16%
Structural Materials
16%
Material Performance
16%
Material Behavior
16%
Reactor Technology
16%
Selection Criterion
16%
Earth and Planetary Sciences
Molten Salt
83%
Decommissioning
10%
Nuclear Fuel
7%
Radiation Dose
7%
Nuclear Reactor
7%
Radioactive Isotope
7%