1 MeV
2.4 MeV
4.3 MeV
7.8 MeV
D. 7.8 MeV
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
Gas cooled
Liquid metal cooled
Pressurised water
Boiling water
More
Less
Same
Zero
Pressurised water
Boiling water
Gas cooled
Liquid metal cooled
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
For boiling pi water in the core
To use liquid sodium metal as coolant
To use intermediate coolant
To prevent the water coolant from boiling in the core
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%
Kinetic energy of neutrons
Kinetic energy of fission products
Instantaneous release of gamma rays
Gradual radioactive decay of fission products
U₂₃₃ and Pu₂₂₉
U₂₃₁ and Pu₂₃₃
U₂₃₅ and Pu₂₃₅
U₂₃₈ and Pu₂₃₉
To maintain constant pressure in primary circuit under varying load
To Supply high pressure steam
To increase pressure of water in primary circuit
To provide sub cooled water at high pressure
Same
More
Less
There is no such criterion
Control temperature
Control radioactive pollution
Control absorption of neutron
Control fuel consumption
Same
More
Less
May be less or mote depending on size
Heavy water
Concrete and bricks
Graphite and concrete
Graphite
U₂₃₃ and Pu₂₃₉
U
U₂₃₈ and Pu₂₃₉
U₂₃₈ and Th₂₃₉
Lead or concrete
Lead and tin
Graphite or cadmium
Thick galvanised sheets
Light weight atoms
Heavy weight atoms
Critical atoms
Zero weight atoms
Carbon
Lead
Concrete
All of these
Maximum in centre and zero at side
Maximum at side and zero in canter
Uniform throughout
Zero throughout
Heavy water
Graphite
Carbon dioxide
No moderator is needed
2.46
24.6
246
2460
Unity
More than unity
Less than unity
Zero
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
The most fissionable material
The basic fuel for nuclear paints
Basic raw material for nuclear plants
The material which absorbs neutrons and undergoes spontaneous changes leading to the formation of fissionable material
Does not absorb neutrons
Absorbs neutrons
Accelerates neutrons
Eats up neutrons
Any type of moderator can be used
Graphite is used as the moderator
Heavy water is used as the moderator
Moderator is dispensed with.
U₂₃₄
U₂₃₅
U₂₃₈
All of these
Greater than 1.0
Less than 1.0
Equal to zero
Equal to 1.0