Artificially
By fission of Th₂₃₂
When U₂₃₈ is irradiated by neutrons
As basic raw material
C. When U₂₃₈ is irradiated by neutrons
U₂₃₅
U₂₃₈
Pu₂₃₃
Pu₂₃₉
More
Less
Same
Zero
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
Light weight atoms
Heavy weight atoms
Critical atoms
Zero weight atoms
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
Regenerative reactor
Fast breeder reactor
Breeder reactor
Boiling water reactor
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
Increased production of neutrons
Complete absorption of neutrons
Controlled production of neutrons
Decreased leakage of neutrons
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%
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
Natural uranium
Molten lead
Any form of uranium
Thorium
CO2
Pressurised water
Mixture of water and steam
Liquid metal
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
Gas cooled
Liquid metal cooled
Pressurised water
Boiling water
Enriched uranium
Plutonium
Thorium
U₂₃₅
2.46
24.6
246
2460
Power generation
Nucleonic devices
Nuclear fission
Medical field
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
Heavy water
Graphite
Carbon dioxide
No moderator is needed
Atomic power
Energy
Voltage
Radio activity
To produce heat for thermoelectric power
To produce fissionable material
To propel ships, submarines, aircrafts
All of these
Alpha particles
Beta particles
Thermal neutrons
Fast neutrons and gamma rays
High neutron absorption cross-section
Low moderating efficiency
High neutron scatter cross-section
Low neutron absorption cross-section
Same
More
Less
May be less or mote depending on size
1-99 %
1-25 %
1-50 %
1-75 %
Any type of moderator can be used
Graphite is used as the moderator
Heavy water is used as the moderator
Moderator is dispensed with.
It produces more fuel than it consumes.
It requires highly enriched fuel.
It requires liquid sodium metal as moderator.
All of the above
Slowing down fast neutrons so that Uz fission continues by slow motion neutrons
Accelerating fast neutrons
Absorbing all neutrons
Using moderator
Same
Lower
Higher
Unity
Protons and neutrons in an atom
Protons and electrons in an atom
Neutrons and electrons in an atom
Protons and neutrons in a nucleus