Light or heavy water
Molten lead
Carbon dioxide
Freon
Mass number
Atomic number
Chemical properties
Position in periodic table
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
X-rays
Infrared rays
Neutrons and gamma rays
Electrons
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
Ordinary fluid
Heavy water
Molten lead
Hydrogen gas
Is lighter
Is inert
Has high specific heat
Is a good conductor
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
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
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
MeV
Curie
Farads
MW
Pressurised water
Boiling water
Gas cooled
Liquid metal cooled
Heavy water
Concrete and bricks
Graphite and concrete
Graphite
More
Less
Same
Zero
As basic raw material
By neutron irradiation of Uz
By neutron irradiation of thorium
Artificially
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Heavy water
Graphite
Carbon dioxide
No moderator is needed
Enriched uranium
Plutonium
Thorium
U
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
Natural uranium
Enriched uranium
Pure uranium
Any type of uranium
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Does not absorb neutrons
Absorbs neutrons
Accelerates neutrons
Eats up neutrons
2.46
24.6
246
2460
Artificially
By fission of Th₂₃₂
When U₂₃₈ is irradiated by neutrons
As basic raw material
Carbon
Lead
Concrete
All of these
Atomic power
Energy
Voltage
Radio activity
Demineralised water
Carbon dioxide
Heavy water
No moderator is used