Nuclear Power Engineering A fast breeder reactor employs Water as coolant Graphite as moderator Molten sodium as coolant as well as moderator U-235 as fuel Water as coolant Graphite as moderator Molten sodium as coolant as well as moderator U-235 as fuel ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Which of the following gases has very high neutron capture cross-section, making it unsuitable as a coolant in nuclear reactor? CO₂ He H₂ N₂ CO₂ He H₂ N₂ ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Thermal nuclear reactors using enriched uranium as fuel contains a maximum of __________ percent fissile material i.e. U-235. 1 3 7 2 1 3 7 2 ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Uranium percentage in monazite sand is about 0.25 0.01 7 1.2 0.25 0.01 7 1.2 ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Percentage of U-238 in natural uranium is around 0.015 0.71 99.29 29.71 0.015 0.71 99.29 29.71 ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Heavy water (D₂O) in a nuclear reactor serves as a Moderator Both A & B Coolant Neutron absorber Moderator Both A & B Coolant Neutron absorber ANSWER DOWNLOAD EXAMIANS APP
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