CONCEPTUAL DESIGN OF TEMPERATURE-CONTROLLED FUELED-SALT IRRADIATION EXPERIMENT TO SUPPORT DEMONSTRATION OF ADVANCED NUCLEAR REACTORS

Keyphrases

• Reactor 100%
• Advanced Reactors 100%
• Irradiation Experiment 100%
• Temperature Control 100%
• Molten Salt 33%
• Thermal Analysis 33%
• Neutronic Analysis 33%
• Radiation Test 33%
• Design Parameters 33%
• Idaho National Laboratory 33%
• Safety Parameters 33%
• Neutronics 33%
• Safety Margin 33%
• Fuel Enrichment 33%
• Burnup 33%
• Molten Salt Reactor 33%
• Reactor Design 33%
• Structural Materials 33%
• Reactor Safety 33%
• Thermophysical Properties 33%
• Mechanical Analysis 33%
• Irradiation Capsule 33%
• Annulus 33%
• In-pile Irradiation 33%
• High Temperature Molten Salt 33%
• Fuel Salt 33%
• High-temperature Alloys 33%
• Thermal Design 33%
• Design Objectives 33%
• Source Term Model 33%

Engineering

• Neutronics 100%
• Advanced Nuclear Reactor 100%
• Molten Salt 100%
• Burnup 50%
• Safety Margin 50%
• Molten Salt Reactor 50%
• Reactor Design 50%
• Structural Materials 50%
• Reactor Safety 50%
• Source Term 50%
• Parametric Study 50%
• Design Objective 50%

Chemical Engineering

• Neutronics 100%