Nuclear Power Engineering

A. Candu reactor
B. Fast breeder reactor
C. Homogeneous reactor
D. Pressurised water reactor

A. Insulation lining of the reactor
B. Fuel
C. Lubricant
D. Retarder of neutron velocity

A. Absence of earthquake prone zone in nearby areas
B. Abundant availability of water
C. Remotely located from residential areas
D. Proximity to fuel source

A. The production of radioisotopes
B. Supplying intense fields or beams of neutron for scientific experiments
C. Marine ship propulsion
D. None of these

A. Rapid heat transfer from the core
B. Accelerating the reaction rate in the core
C. Breeding neutrons
D. Accelerating the neutrons

A. Number of neutrons
B. Mass number
C. Electronic configuration
D. Atomic weight

A. Liquid metal cooled
B. Fast breeder
C. Thermal
D. Swimming pool

A. 3
B. 235
C. 200
D. 92

A. Electron capture
B. β-emission
C. α-emission
D. Positron emission

A. Chain reaction and hence the power output by regulating the number of secondary neutrons
causing fission
B. Emission of hazardous radiation
C. Conversion of fissile material into fertile material
D. Velocity of the secondary neutrons