9 results on '"Sun, Kaichao"'
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2. Experimental validation of a high fidelity Monte Carlo neutron transport model of the MIT graphite exponential pile
3. Tritium generation, release, and retention from in-core fluoride salt irradiations
4. Machine learning based system performance prediction model for reactor control
5. Estimate of radiation release from MIT reactor with un-finned LEU core during Maximum Hypothetical Accident
6. Investigation on mitigating neutron streaming effect for the water-loop facility used in the MIT reactor
7. Validation of a fuel management code MCODE-FM against fission product poisoning and flux wire measurements of the MIT reactor
8. A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
9. Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
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