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(a) same
(b) more
(c) less
(d) may be less or mote depending on size
(e) unpredictable.
Ans: c
(a) same atomic number and different mas-ses
(b) same chemical properties but different atomic numbers
(c) different masses and different atomic numbers
(d) different chemical properties and same atomic numbers
(e) same chemical properties and same atomic numbers.
Ans: b
(a) protons in the nucleus
(b) electrons in me nucleus
(c) neutrons in the nucleus
(d) electrons in the atom
(e) neutrons in the atom.
Ans: a
(a) protons and neutrons in an atom
(b) protons and electrons in an atom
(c) neutrons and electrons in an atom
(d) protons and neutrons in a nucleus
(e) protons and electrons in a nucleus.
Ans: d
(a) mass number
(b) atomic number
(c) chemical properties
(d) position in periodic table
(e) all of the above.
Ans: a
(a) U233andPu239
(b) U23iandPu233
(c) U235andPu235
(d) U238andPu239
(e) U243andPu235
Ans: a
(a) it is generating power to rated capacity
(b) it is capable of generating much more than rated capacity
(c) there is danger of nuclear spread
(d) chain reaction that causes automatic splitting of the fuel nuclei has been es-tablished
(e) it generates no heat.
Ans: d
(a) reduce temperature
(b) extract heat from nuclear reaction
(c) control the reaction
(d) cause collision with the fast moving neutrons to reduce their speed
(e) moderate the radioactive pollution.
Ans: d
(a) heavy water
(b) concrete and bricks
(c) graphite and concrete
(d) deutrium
(e) graphite.
Ans: e
(a) MeV
(b) curie
(c) farads
(d) MW
(e) kWhr.
Ans: a
(a) 5 MeV
(b) 10 MeV
(c) 199 MeV
(d) 168 MeV
(e) 11 MeV.
Ans: c
(a) unity
(b) more than unity
(c) less than unity
(d) zero
(e) infinity.
Ans: b
(a) boiler
(b) direct cycle of coolant system
(c) double circuit system of coolant cycle
(d) multi pass system
(e) single circuit system.
Ans: b
(a) boiler
(b) direct cycle of coolant system
(c) double circuit system of coolant cycle
(d) multi pass system
(e) single circuit system.
Ans: c
(a) 1 tonne of high grade coal
(b) 4.5 tonnes of high grade coal
(c) 10 tonnes of high grade coal
(d) 100 tonnes of high grade coal
(e) 1000 tonnes of high grade coal.
Ans: b
(a) gas cooled
(b) liquid metal cooled
(c) pressurised water
(d) boiling water
(e) none of the above.
Ans: d
(a) 1
(b) 2
(c) U
(c) 3
(e) 0
Ans: c
(a) lead or concrete
(b) lead and tin
(c) graphite or cadmium
(d) thick galvanised sheets
(e) black carbon papers.
Ans: a
(a) X-rays
(b) infra-red rays
(c) a, P, and y rays
(d) neutrons and gamma rays
(e) electrons.
Ans: d
(a) return the neutrons back into the core
(b) shield the radioactivity completely
(c) check polllution
(d) conserve energy
(e) is not used.
Ans: a
(a) 1 MeV
(b) 2.4 MeV
(c) 4.3 MeV
(d) 7.8 MeV
(e) 20 MeV.
Ans: d
(a) U233andPu239
(b) U
(c) U238andPu239
(d) U238andTh239
(e) none of the above
Ans: b
(a) the most fissionable material
(b) the basic fuel for nuclear paints
(c) basic raw material for nuclear plants
(d) the material which absorbs neutrons and undergoes spontaneous changes leading to the formation of fissionable material
(e) none of the above.
Ans: d
(a) %age of U235 has been artificially in-creased
(b) %age of U has been artificially in¬creased
(c) %age of U234 has been artificially in-creased
(d) extra energy is pumped from outside
(e) all impurities have been removed.
Ans: a
(a) nucleus
(b) electron
(c) proton
(d) meson
(e) neutron.
Ans: b
(a) neutron
(b) proton
(c) atom
(d) electron
(e) nucleus.
Ans: c
(a) any type of moderator can be used
(b) graphite is used as the moderator
(c) heavy water is used as the moderator
(d) moderator may or may not be used
(e) moderator is dispensed with.
Ans: e
(a) no new neutron
(b) at least one new neutron
(c) one new neutron
(d) more than one new neutrons
(e) many-fold neutrons.
Ans: d
(a) same
(b) lower
(c) higher
(d) unity
(e) higher/lower depending on the size of reactor.
Ans: b
(a) graphite, C02
(b) graphite, air
(c) heavy water, C02
(d) lead, H2
(e) concrete, N2.
Ans: a
(a) 20
(b) 200
(c) 2000
(d) 20,000
(e) 2 x 105.
Ans: b
(a) splitting
(b) fission
(c) fusion
(d) disintegration
(e) chain reaction.
Ans: b
(a) same
(b) more
(c) less
(d) there is no such criterion
(e) none of the above.
Ans: b
(a) demineralised water
(b) carbon dioxide
(c) heavy water
(d) graphite
(e) no moderator is used.
Ans: e
(a) Kota
(b) Kalapakkam
(c) Tarapur
(d) Baraeilly
(e) Kerala.
Ans: c
(a) fast breeder
(b) pressurised water
(c) boiling water
(d) sodium graphite
(e) none of the above.
Ans: c
(a) ordinary fluid
(b) heavy water
(c) molten lead
(d) hydrogen gas
(e) none of the above.
Ans: a
(a) maximum in centre and zero at side
(b) maximum at side and zero in centre
(c) uniform throughout
(d) zero throughout
(e) none of the above.
Ans: c
(a) 1-99%
(b) 1-25%
(c) 1-50%
(d) 1-75%
(e) 1-90%.
Ans: a
(a) high energy (fast) neutrons alone
(b) low energy (slow) neutrons alone
(c) either fast or slow neutrons
(d) medium energy neutrons
(e) none of the above.
Ans: c
(a) high energy (fast) neutrons alone
(b) low energy (slow) neutrons alone
(c) either fast or slow neutrons
(d) medium energy neutrons
(e) none of the above.
Ans: a
(a) regenerative reactor
(b) fast breeder reactor
(c) breeder reactor
(d) boiling water reactor
(e) ferrite reactor.
Ans: a
(a) is lighter
(b) is inert
(c) has high specific heat
(d) is a good conductor
(e) all of the above.
Ans: c
(a) 99.282% U238, 0.712% U235, 0.006% U234
(b) 99.282% U235, 0.712% U238, 0.06%' U234
(c) 99.282% U234, 0.712% U238, 0.006% U235
(d) 99.282% U235, 0.712% U234, 0.006% U238
(e) none of the above.
Ans: a
(a) pressurised water
(b) boiling water
(c) gas cooled
(d) liquid metal cooled
(e) all of the above.
Ans: b
(a) as basic raw material
(b) by neutron irradiation of Uz
(c) by neutron irradiation of throium
(d) artificially
(e) in high capacity furnace.
Ans: b
(a) atomic power
(b) energy
(c) voltage
(d) radio activity
(e) there is no such unit.
Ans: b
(a) In a heterogeneous or solid-fuel reactor, the fuel is mixed in a regular pattern within moderator.
(b) Slow or thermal neutrons have energy of the order or 0.025 eV
(c) Fast neutrons have energies above 1000 eV
(d) Fast reactor uses moderator
(e) Most serious drawback in using water as coolant in nuclear plants is its high vapour pressure.
Ans: d
(a) electron-volt
(b) electron-ampere
(c) curie
(d) MeV
(e) AMU.
Ans: c
(a) operate at extremely high power den-sities.
(b) are liquid-metal cooled
(c) produce more fuel than they consume
(d) are unmoderated
(e) use water as coolant.
Ans: e
(a) as basic raw material
(b) by neutron irradiation of Uz
(c) by neutron irradiation of thorium
(d) artificially
(e) in high capacity furnaces.
Ans: c
(a) as basic raw material
(b) by neutron irradiation of IT*
(c) by neutron irradiation of thorium
(d) artificially
(e) in high capacity furnaces.
Ans: b
(a) centrifugal
(b) axial
(c) reciprocation
(d) electromagnetic
(e) diaphragm.
Ans: d
(a) Ulii
(b) U
(c) U238
(d) Pu:
(e) Pu
Ans: b
(a) Th232andU238
(b) U233andPu239
(c) U233andPu238
Ans: c
(a) to maintain constant pressure in primary circuit under varying load
(b) to Supply high pressure steam
(c) to increase pressure of water in primary circut
(d) to provide subcooled water at high pressure
(e) all of the above.
Ans: a
(a) light or heavy water
(b) molten lead
(c) carbon dioxide
(d) freon
(e) carbon tetrachloride.
Ans: a
(a) natural uranium
(b) molten lead
(c) any form of uranium
(d) thorium
(e) plutonium.
Ans: b
(a) control temperature
(b) control readioactive pollution
(c) control absorption of neutron
(d) control fuel consumption
(e) none of the above.
Ans: c
(a) acts as good moderator
(b) produces maximum steam
(c) transfers heat from core at a fast rate
(d) breeds neutrons
(e) increases rate of reaction in core.
Ans: c
(a) fast
(b) slow
(c) in bulk
(d) static
(e) activated.
Ans: b
(a) used fuel should be reprocessed
(b) moderator should be used
(c) coolant should be employed
(d) control rods should be used
(e) reflector should be used.
Ans: a
(a) chain reaction can be initiated
(b) it becomes uncontrollable
(c) it explodes
(d) it produces no power
(e) it produces tremendous power.
Ans: a
(a) infinite
(b) zero
(c) exactly balanced by the loss of neutrons through leakage
(d) initiated
(e) stopped.
Ans: c
(a) at the lower rate than the consumption
(b) at a higher rate than the constuption
(c) at an equal rate of the consumption
(d) depends on other considerations
(e) unpredictable.
Ans: b
(a) almost same
(b) slightly more
(c) slightly less
(d) much less
(e) much more.
Ans: d
(a) natural uranium
(b) enriched uranium
(c) pure uranium
(d) any type of uranium
(e) none of the above.
Ans: b
(a) boiling water
(b) gas cooled
(c) pressurised water
(d) all of the above
(e) none of the above.
Ans: b
(a) plates
(b) pallets
(c) pins
(d) any one of the above
(e) none of the above.
Ans: d
(a) does not absorb neutrons
(b) absorbs neutrons
(c) accelerates neutrons
(d) eats up neutrons
(e) regenerates neutrons.
Ans: a
(a) slowing down fast neutrons so that Uz fission continues by slow motion neutrons
(b) accelerating fast neutrons
(c) absorbing all neutrons
(d) using moderator
(e) enriching U235.
Ans: a
(a) fast moving
(b) slow moving
(c) critical neutrons
(d) neutrons at rest
(e) none of the above.
Ans: b
(a) light weight atoms
(b) heavy weight atoms
(c) critical atoms
(d) zero weight atoms
(e) there is no such criterion.
Ans: a
(a) kinetic energy of neutrons
(b) kinetic energy of fission products
(c) instantaneous release of gamma rays
(d) gradual readioactive decay of fission products
(e) none of the above.
Ans: b
(a) alpha particles
(b) beta particles
(c) thermal neutrons
(d) fast neutrons and gamma rays
(e) none of the above.
Ans: d
(a) the original elements change into com-pletely different elements
(b) the electrons of the element change
(c) the molecules rearrange themselves to form other molecules
(d) none of the above.
Ans: a
(a) greater than 1.0
(b) less than 1.0
(c) equal to zero
(d) equal to 1.0
(e) equal to infinity.
Ans: d
(a) 1 neutron
(b) 1 — neutrons
(c) 1 - 2 neutrons
(d) 2 — neutrons
(e) infinite.
Ans: d
(a) enriched uranium
(b) plutonium
(c) thorium
(d) U235
(e) natrual uranium.
Ans: d
(a) enriched uranium
(b) plutonium
(c) thorium
(d) U
(e) natural uranium.
Ans: a
(a) uses graphite rods as moderator
(b) has powerful moderator
(c) has no moderator
(d) uses ferrite material as moderator
(e) uses pressurised water as moderator.
Ans: c
(a) power generation
(b) nucleonic devices
(c) nuclear fission
(d) nuclear fusion
(e) medical field.
Ans: e
(a) 90% U-235
(b) U-238
(c) U-235
(d) Pu-239
(e) U-239.
Ans: a
(a) electrons
(b) protons
(c) neutrons
(d) nulceus
(e) atom.
Ans: e
(a) for boiling pi water in the core
(b) to use liquid sodium metal as coolant
(c) to use intermediate coolant
(d) to prevent the water coolant from boil¬ing in the core
(e) to eliminate the coolant loop of the pressurised water.
Ans: d
(a) C02
(b) pressurised water
(c) mixture of water and steam
(d) liquid metal
(e) mercury.
Ans: c
(a) coolant itself
(b) ferrite rod
(c) graphite rod
(d) liquid sodium metal
(e) blanket of thorium.
Ans: a
(a) plutonium
(b) uranium
(c) deuterium
(d) thorium
(e) lithium.
Ans: c
(a) higher cost of nuclear fuel
(b) high initial cost
(c) high heat rejection in condenser
(d) lower temperature and pressure condi-tions
(e) nuclear hazard risk.
Ans: d
(a) increased production of neutrons
(b) complete absorption of neutrons
(c) controlled production of neutrons
(d) decreased leakage of neutrons
(e) decrease of speed of neutrons.
Ans: d
(a) more
(b) less
(c) same
(d) zero
(e) negative, i.e. fuel would be generated.
Ans: b