Neutronics investigation of CANada Deuterium Uranium 6 reactor fueled (transuranic–Th) O2 using a computational method
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
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1. Searching for incinerating the accumulated plutonium around the world by mixing it with thorium and using this mixture as a nuclear fuel in the CANDU-6;Nuclear Engineering and Technology;2024-08
2. Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor;Nuclear Engineering and Design;2022-11
3. Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor;Nuclear Technology and Radiation Protection;2022
4. Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes;Radiation Physics and Chemistry;2019-07
5. Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor;Nuclear Science and Engineering;2019-06-17
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