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Graphite Licensing (ASME) and Testing (ASTM) Technical Assistance
Michael E Davenport
Nuclear Fuels & Materials
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Dive into the research topics of 'Graphite Licensing (ASME) and Testing (ASTM) Technical Assistance'. Together they form a unique fingerprint.
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Keyphrases
High-temperature Reactor
100%
Graphite
100%
American Society
100%
Technical Assistance
100%
Pressure Vessel Code
75%
Boiler Pressure
75%
Material Properties
50%
Graphite Components
50%
Operating Conditions
25%
Neutron Flux
25%
Reactor Core
25%
R&D Programs
25%
Reactor Design
25%
Elevated Temperature
25%
Property Change
25%
Testing Method
25%
Environmental Conditions
25%
Environmental Degradation
25%
Structural Integrity
25%
Standardized Tests
25%
Neutron Radiation
25%
Irradiation Response
25%
Sample Testing
25%
Nuclear Graphite
25%
ASME Code
25%
Graphite Core
25%
Radiation Flux
25%
Elevated Temperature Test
25%
Oxidation Response
25%
Property Testing
25%
New Americans
25%
Structural Design Codes
25%
Structural Codes
25%
Engineering
High Temperature Reactors
100%
Pressure Vessel Codes
75%
Boiler Pressure
75%
Elevated Temperature
50%
Reactor Core
25%
Reactor Design
25%
Neutron Flux
25%
Structural Integrity
25%
Testing Method
25%
Operational Condition
25%
Design Code
25%
Structural Design
25%
Computer Science
Structural Integrity
100%
Operational Condition
100%
Core Component
100%
Standardized Test
100%
Structural Design
100%
Earth and Planetary Sciences
Pressure Vessel
100%
Reactor Core
33%
Flux (Rate)
33%
Environmental Degradation
33%
Property of Materials
33%
Testing Method
33%
Biochemistry, Genetics and Molecular Biology
Neutron Radiation
100%
Reactor Design
50%