Demineralised water
Carbon dioxide
Heavy water
No moderator is used
High neutron absorption cross-section
Low moderating efficiency
High neutron scatter cross-section
Low neutron absorption cross-section
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
Protons and neutrons in an atom
Protons and electrons in an atom
Neutrons and electrons in an atom
Protons and neutrons in a nucleus
Same
More
Less
There is no such criterion
Ordinary fluid
Heavy water
Molten lead
Hydrogen gas
Absorbs neutrons
Does not absorb neutrons
Accelerates neutrons
None of these
Natural uranium
Molten lead
Any form of uranium
Thorium
The original elements change into completely different elements
The electrons of the element change
The molecules rearrange themselves to form other molecules
None of the above
Maximum in centre and zero at side
Maximum at side and zero in canter
Uniform throughout
Zero throughout
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
CO2
Pressurised water
Mixture of water and steam
Liquid metal
Used fuel should be reprocessed
Moderator should be used
Coolant should be employed
Control rods should be used
U₂₃₃ and Pu₂₃₉
U₂₃₅ and Th₂₃₂
U₂₃₅ and Pu₂₃₈
U₂₃₃ and Pu₂₃₈
Fast moving
Slow moving
Critical neutrons
Neutrons at rest
Nucleus
Electron
Proton
Meson
Kinetic energy of neutrons
Kinetic energy of fission products
Instantaneous release of gamma rays
Gradual radioactive decay of fission products
Greater than 1.0
Less than 1.0
Equal to zero
Equal to 1.0
100
200
300
400
In a heterogeneous or solid fuel reactor, the fuel is mixed in a regular pattern within moderator.
Slow or thermal neutrons have energy of the order or 0.025 eV
Fast neutrons have energies above 1000 eV
Fast reactor uses moderator
Steam power plant
Gas turbine power plant
Hydro electric power plant
Nuclear power plant
Any form of uranium
Natural uranium
Enriched uranium
Plutonium
U₂₃₃ and Pu₂₃₉
U
U₂₃₈ and Pu₂₃₉
U₂₃₈ and Th₂₃₉
Reduce temperature
Extract heat from nuclear reaction
Control the reaction
Cause collision with the fast moving neutrons to reduce their speed
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
1 MeV
2.4 MeV
4.3 MeV
7.8 MeV
Slowing down fast neutrons so that Uz fission continues by slow motion neutrons
Accelerating fast neutrons
Absorbing all neutrons
Using moderator
U₂₃₄ = 0.006%, U₂₃₅ = 0.712% and U₂₃₈ = 99.282%
U₂₃₄ = 0.712%, U₂₃₅ = 0.006% and U₂₃₈ = 99.282%
U₂₃₄ = 99.282%, U₂₃₅ = 0.006% and U₂₃₈ = 0.712%
U₂₃₄ = 0.006%, U₂₃₅ = 99.282% and U₂₃₈ = 0.712%
Mass number
Atomic number
Chemical properties
Position in periodic table
Electron volt
Electron ampere
Curie
MV