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
A. 99.282% U₂₃₈, 0.712% U₂₃₅, 0.006% U₂₃₄
Carbon
Lead
Concrete
All of these
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
It produces more fuel than it consumes.
It requires highly enriched fuel.
It requires liquid sodium metal as moderator.
All of the above
By increasing the contents of U₂₃₅
By slowing down fast neutrons so that U₂₃₅ fission continues by slow neutron
Both (A) and (B)
None of these
Protons in the nucleus
Electrons in the nucleus
Neutrons in the nucleus
Electrons in the atom
Splitting
Fission
Fusion
Disintegration
Graphite
Heavy water
Concrete
Graphite and concrete
Maximum in centre and zero at side
Maximum at side and zero in canter
Uniform throughout
Zero throughout
CO2
Pressurised water
Mixture of water and steam
Liquid metal
Increased production of neutrons
Complete absorption of neutrons
Controlled production of neutrons
Decreased leakage of neutrons
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
Electrons
Protons
Neutrons
Atom
Steam power plant
Gas turbine power plant
Hydro electric power plant
Nuclear power plant
High neutron absorption cross-section
Low moderating efficiency
High neutron scatter cross-section
Low neutron absorption cross-section
Ordinary fluid
Heavy water
Molten lead
Hydrogen gas
Increases
Decreases
Have no effect on
None of these
Return the neutrons back into the core
Shield the radioactivity completely
Check pollution
Conserve energy
Infinite
Zero
Exactly balanced by the loss of neutrons through leakage
Initiated
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
Percentage of U₂₃₅ has been artificially increased
Percentage of U has been artificially increased
Percentage of U₂₃₄ has been artificially increased
Extra energy is pumped from outside
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
Heavy water
Graphite
Carbon dioxide
No moderator is needed
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
To produce heat for thermoelectric power
To produce fissionable material
To propel ships, submarines, aircrafts
All of these
More
Less
Same
Zero
Boiling water
Gas cooled
Pressurised water
All of the above
Natural uranium
Molten lead
Any form of uranium
Thorium
Unity
More than unity
Less than unity
Zero
Any type of moderator can be used
Graphite is used as the moderator
Heavy water is used as the moderator
Moderator is dispensed with.
Fast
Slow
In bulk
Static