High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
C. Either fast or slow neutrons
Same atomic number and different masses
Same chemical properties but different atomic numbers
Different masses and different atomic numbers
Different chemical properties and same atomic numbers
Artificially
By fission of Th₂₃₂
When U₂₃₈ is irradiated by neutrons
As basic raw material
Increases
Decreases
Have no effect on
None of these
U₂₃₃ and Pu₂₃₉
U
U₂₃₈ and Pu₂₃₉
U₂₃₈ and Th₂₃₉
Enriched uranium
Plutonium
Thorium
U
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
Control temperature
Control radioactive pollution
Control absorption of neutron
Control fuel consumption
Operate at extremely high power densities.
Are liquid metal cooled
Produce more fuel than they consume
Use water as coolant
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
Used fuel should be reprocessed
Moderator should be used
Coolant should be employed
Control rods should be used
U₂₃₅
U₂₃₈
Pu₂₃₃
Pu₂₃₉
Carbon
Lead
Concrete
All of these
Boiling water
Gas cooled
Pressurised water
All of the above
Nucleus
Electron
Proton
Meson
Coolant itself
Ferrite rod
Graphite rod
Liquid sodium metal
Light weight atoms
Heavy weight atoms
Critical atoms
Zero weight atoms
Any form of uranium
Natural uranium
Enriched uranium
Plutonium
Uses graphite rods as moderator
Has powerful moderator
Has no moderator
Uses ferrite material as moderator
Centrifugal
Axial
Reciprocation
Electromagnetic
1-99 %
1-25 %
1-50 %
1-75 %
Enriched uranium
Plutonium
Thorium
U₂₃₅
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Same
More
Less
May be less or mote depending on size
U₂₃₄
U₂₃₅
U₂₃₈
All of these
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
U₂₃₃ and Pu₂₂₉
U₂₃₁ and Pu₂₃₃
U₂₃₅ and Pu₂₃₅
U₂₃₈ and Pu₂₃₉
Infinite
Zero
Exactly balanced by the loss of neutrons through leakage
Initiated
Fast
Slow
In bulk
Static
Heavy water
Concrete and bricks
Graphite and concrete
Graphite