Nuclear Power Engineering Nuclear fuel complex, Hyderabad is engaged in the job of Manufacture of nuclear fuel elements/assemblies Treatment of spent fuel Processing of uranium ore None of these Manufacture of nuclear fuel elements/assemblies Treatment of spent fuel Processing of uranium ore None of these ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Secondary cooling circuit is a must in molten sodium cooled fast breeder reactor for Faster heat removal rate from the core Achieving high degree of superheat in the steam Avoiding the mixing of water with radioactive sodium, as it may cause explosion Lowering the coolant circulation pressure Faster heat removal rate from the core Achieving high degree of superheat in the steam Avoiding the mixing of water with radioactive sodium, as it may cause explosion Lowering the coolant circulation pressure ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering In a pressurised water reactor (PWR), the Coolant water boils in the core of the reactor Fuel is natural uranium and heavy water acts both as moderator & coolant Coolant water is pressurised to prevent bulk boiling of water in the core Use of moderator is not required Coolant water boils in the core of the reactor Fuel is natural uranium and heavy water acts both as moderator & coolant Coolant water is pressurised to prevent bulk boiling of water in the core Use of moderator is not required ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Moderating material used in a thermal-reactor should be a Poor absorber of neutrons None of these Solid substance Good absorber of neutrons Poor absorber of neutrons None of these Solid substance Good absorber of neutrons ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Thorium⁻²32 (a fertile material) on absorption of a neutron gets converted into __________ , which is a fissile material. Plutonium⁻²39 Uranium⁻²33 Thorium⁻²33 Uranium⁻²35 Plutonium⁻²39 Uranium⁻²33 Thorium⁻²33 Uranium⁻²35 ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Molten sodium is used as a coolant in a fast breeder reactor, because of its Excellent moderating properties Faster heat removal capability from the core Capability to increase the reaction rate in the core Neutron breeding capability Excellent moderating properties Faster heat removal capability from the core Capability to increase the reaction rate in the core Neutron breeding capability ANSWER DOWNLOAD EXAMIANS APP
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