Lead or concrete
Lead and tin
Graphite or cadmium
Thick galvanised sheets
A. Lead or concrete
Artificially
By fission of Th₂₃₂
When U₂₃₈ is irradiated by neutrons
As basic raw material
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
Gas cooled
Liquid metal cooled
Pressurised water
Boiling water
Enriched uranium
Plutonium
Thorium
U₂₃₅
Graphite
Heavy water
Concrete
Graphite and concrete
99.282% U₂₃₈, 0.712% U₂₃₅, 0.006% U₂₃₄
99.282% U₂₃₅, 0.712% U₂₃₈, 0.06%' U₂₃₄
99.282% U₂₃₄, 0.712% U₂₃₈, 0.006% U₂₃₅
99.282% U₂₃₅, 0.712% U₂₃₄, 0.006% U₂₃₈
Enriched uranium
Plutonium
Thorium
U
Splitting
Fission
Fusion
Disintegration
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
Uses graphite rods as moderator
Has powerful moderator
Has no moderator
Uses ferrite material as moderator
U₂₃₅
U₂₃₈
Pu₂₃₃
Pu₂₃₉
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
Regenerative reactor
Fast breeder reactor
Breeder reactor
Boiling water reactor
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
Neutron
Proton
Atom
Electron
It is generating power to rated capacity
It is capable of generating much more than rated capacity
There is danger of nuclear spread
Chain reaction that causes automatic splitting of the fuel nuclei has been established
Kinetic energy of neutrons
Kinetic energy of fission products
Instantaneous release of gamma rays
Gradual radioactive decay of fission products
U₂₃₃ and Pu₂₃₉
U
U₂₃₈ and Pu₂₃₉
U₂₃₈ and Th₂₃₉
Acts as good moderator
Produces maximum steam
Transfers heat from core at a fast rate
Breeds neutrons
Carbon
Lead
Concrete
All of these
Ordinary fluid
Heavy water
Molten lead
Hydrogen gas
5 MeV
10 MeV
199 MeV
168 MeV
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
More
Less
Same
Zero
Stable under nuclear radiation
Corrosion resistant
Good thermal conductor
All of these
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
Absorbs neutrons
Does not absorb neutrons
Accelerates neutrons
None of these