Assessment of Fission Product Release in High-Temperature Gas-Cooled Reactors using TRISO Fuel for Radiological Consequence Assessment
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Shah, Manit [ORNL] (ORCID:0000000236009504)↗
Engineering topics
Shah, Manit [ORNL] (ORCID:0000000236009504)
Publications and source records attributed to Shah, Manit [ORNL] (ORCID:0000000236009504).
Measurement Strategies for Nuclear Material Holdup in Liquid-Fueled Molten Salt Reactors with Circulating Fuel
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Shah, Manit [ORNL] (ORCID:0000000236009504)↗
MELCOR Model Development for BlueCRAB and FATE Microreactor Code Comparisons
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Shah, Manit [ORNL] (ORCID:0000000236009504)↗
Assessment of Fission Product Release Behavior in Sodium-Cooled Fast Reactors for Consequence Assessment
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Shah, Manit [ORNL] (ORCID:0000000236009504)↗