Absorb excess neutrons
Control fuel consumption
Control temperature
All of these
A. Absorb excess neutrons
Increased production of neutrons
Complete absorption of neutrons
Controlled production of neutrons
Decreased leakage of neutrons
U₂₃₅
U₂₃₈
Pu₂₃₉
Pu₂₃₃
Graphite, CO2
Graphite, air
Heavy water, CO2
Lead, H2
Same
More
Less
May be less or mote depending on size
Coolant itself
Ferrite rod
Graphite rod
Liquid sodium metal
1 neutron
3 neutrons
1, 2 neutrons
2 neutrons
At the lower rate than the consumption
At a higher rate than the consumption
At an equal rate of the consumption
Depends on other considerations
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
Lead or concrete
Lead and tin
Graphite or cadmium
Thick galvanised sheets
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
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Ordinary fluid
Heavy water
Molten lead
Hydrogen gas
Kinetic energy of neutrons
Kinetic energy of fission products
Instantaneous release of gamma rays
Gradual radioactive decay of fission products
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
Natural uranium
Enriched uranium
Pure uranium
Any type of uranium
Almost same
Slightly more
Slightly less
Much less
Operate at extremely high power densities.
Are liquid metal cooled
Produce more fuel than they consume
Use water as coolant
Any type of moderator can be used
Graphite is used as the moderator
Heavy water is used as the moderator
Moderator is dispensed with.
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
Carbon
Lead
Concrete
All of these
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
Does not absorb neutrons
Absorbs neutrons
Accelerates neutrons
Eats up neutrons
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
Gas cooled
Liquid metal cooled
Pressurised water
Boiling water
Mass number
Atomic number
Chemical properties
Position in periodic table
Enriched uranium
Plutonium
Thorium
U₂₃₅
Protons and neutrons in an atom
Protons and electrons in an atom
Neutrons and electrons in an atom
Protons and neutrons in a nucleus
Rapidly increasing leading to the point of explosion
Decreasing from the specified value
Reduced to zero
Constant
1 MeV
2.4 MeV
4.3 MeV
7.8 MeV