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Nuclear Power Engineering

Nuclear Power Engineering
Velocity of the thermal neutron (< 0.025 eV) used for fission of U-235 is around __________ m/sec.

1
3 x 10¹¹
2200
9 x 10²¹

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Nuclear Power Engineering
The critical mass of a fissionable material can be reduced by

Heating it
Surrounding it by neutron reflecting material
Surrounding it by neutron absorbing material
Cooling it

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Nuclear Power Engineering
A fast breeder reactor employs

Molten sodium as coolant as well as moderator
U-235 as fuel
Water as coolant
Graphite as moderator

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Nuclear Power Engineering
Use of molten metal as a coolant in fast breeder reactor helps in

Accelerating the reaction rate in the core
Breeding neutrons
Accelerating the neutrons
Rapid heat transfer from the core

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Nuclear Power Engineering
Heavy water is used as a moderator in a

Candu reactor
Pressurised water reactor (PWR)
Boiling water reactor (BWR)
Molten sodium cooled reactor

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Nuclear Power Engineering
The function of moderators in nuclear reactor is to

Slow down the secondary neutrons
Control the chain reaction
None of these
Absorb the secondary neutrons

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