Rapidly increasing leading to the point of explosion
Decreasing from the specified value
Reduced to zero
Constant
D. Constant
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
Neutron
Proton
Atom
Electron
Steam power plant
Gas turbine power plant
Hydro electric power plant
Nuclear power plant
Absorb excess neutrons
Control fuel consumption
Control temperature
All of these
Electrons
α, β and γ rays
Neutron and gamma rays
None of these
Maximum in centre and zero at side
Maximum at side and zero in canter
Uniform throughout
Zero throughout
Splitting
Fission
Fusion
Disintegration
Reduce temperature
Extract heat from nuclear reaction
Control the reaction
Cause collision with the fast moving neutrons to reduce their speed
Boiling water
Gas cooled
Pressurised water
All of the above
Stable under nuclear radiation
Corrosion resistant
Good thermal conductor
All of these
Artificially
When U238 is irradiated by neutrons
By fission of Th232
As basic raw material
High energy (fast) neutrons alone
Low energy (slow) neutrons alone
Either fast or slow neutrons
Medium energy neutrons
Fast
Slow
In bulk
Static
1 MeV
2.4 MeV
4.3 MeV
7.8 MeV
U₂₃₃ and Pu₂₃₉
U₂₃₅ and Th₂₃₂
U₂₃₅ and Pu₂₃₈
U₂₃₃ and Pu₂₃₈
Increased production of neutrons
Complete absorption of neutrons
Controlled production of neutrons
Decreased leakage of neutrons
Demineralised water
Carbon dioxide
Heavy water
No moderator is used
Slow down the speed of fast moving neutrons
Control the reaction
Reduce the temperature
Extracts heat from nuclear reaction
Uses graphite rods as moderator
Has powerful moderator
Has no moderator
Uses ferrite material as moderator
Return the neutrons back into the core
Shield the radioactivity completely
Check pollution
Conserve energy
Regenerative reactor
Fast breeder reactor
Breeder reactor
Boiling water reactor
1-99 %
1-25 %
1-50 %
1-75 %
Slowing down fast neutrons so that Uz fission continues by slow motion neutrons
Accelerating fast neutrons
Absorbing all neutrons
Using moderator
Boiler
Direct cycle of coolant system
Double circuit system of coolant cycle
Multi passes system
90% U₂₃₅
U₂₃₈
U₂₃₅
Pu₂₃₉
Heavy water
Graphite
Carbon dioxide
No moderator is needed
Same
More
Less
May be less or mote depending on size
Power generation
Nucleonic devices
Nuclear fission
Medical field
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
Centrifugal
Axial
Reciprocation
Electromagnetic