A. all of the above.

C. liquid metal cooled

D. gas cooled

E. pressurised water

B. carbon tetrachloride

C. freon

D. carbon dioxide

E. molten lead

B. unpredictable

C. at the lower rate than the consumption

D. depends on other considerations

E. at an equal rate of the consumption

A. control absorption of neutron

C. none of the above

D. control temperature

E. control fuel consumption

B. zero

C. more

D. same

E. negative, i.e. fuel would be generated

A. all of the above

C. boiling water

D. pressurised water

E. none of the above

A. non oh these

C. U233andPu239

D. Th232andU238

A. are unmoderated

B. are liquid-metal cooled

C. produce more fuel than they consume

E. operate at extremely high power densities.

A. 1-90%.

B. 1-50%

C. 1-75%

D. 1-25%

A. gradual readioactive decay of fission products

B. kinetic energy of neutrons

C. none of the above

D. instantaneous release of gamma rays

A. absorbs neutrons

B. regenerates neutrons

D. accelerates neutrons

E. eats up neutrons

A. produces maximum steam

B. breeds neutrons

D. acts as good moderator

E. increases rate of reaction in core

B. plates

C. pins

D. none of the above

E. pallets

B. it produces no power

C. it explodes

D. it produces tremendous power

E. it becomes uncontrollable

A. 1 neutrons

B. infinite

D. 1 neutron

E. 1 2 neutrons

A. activated

B. static

C. in bulk

E. fast

A. Co2

C. liquid metal

D. mercury

E. pressurised water

A. thorium

B. lithium

D. uranium

E. plutonium

A. reciprocation

B. axial

D. diaphragm

E. centrifugal

A. much more.

B. slightly less

C. almost same

D. slightly more

A. U-239

B. Pu-239

C. U-238

E. U-235

B. U238

C. Pu

D. Pu:

E. Ulii

B. electron-ampere

C. AMU

D. electron-volt

E. MeV

A. plutonium

B. thorium

D. natural uranium.

E. U

A. natural uranium

C. thorium

D. any form of uranium

E. plutonium

B. pure uranium

C. none of the above

D. natural uranium

E. any type of uranium

B. to use intermediate coolant

C. for boiling pi water in the core

D. to eliminate the coolant loop of the pressurised water

E. to use liquid sodium metal as coolant

A. In a heterogeneous or solid-fuel reactor, the fuel is mixed in a regular pattern within moderator.

B. Most serious drawback in using water as coolant in nuclear plants is its high vapour pressure

C. Slow or thermal neutrons have energy of the order or 0.025 eV

D. Fast neutrons have energies above 1000 eV

A. heavy weight atoms

B. there is no such criterion

C. zero weight atoms

D. critical atoms

A. alpha particles

B. beta particles

C. thermal neutrons

E. none of the above

A. to Supply high pressure steam

B. to increase pressure of water in primary circut

C. all of the above

E. to provide subcooled water at high pressure

A. zero

B. stopped

C. initiated

E. infinite

B. none of the above

C. the molecules rearrange themselves to form other molecules

D. strong>. the electrons of the element change

B. by neutron irradiation of thorium

C. as basic raw material

D. in high capacity furnaces

E. artificially

B. nuclear hazard risk

C. high initial cost

D. higher cost of nuclear fuel

E. high heat rejection in condenser

A. nuclear fusion

B. nuclear fission

D. nucleonic devices

E. power generation

A. 99.282% U234, 0.712% U238, 0.006% U235

C. 99.282% U235, 0.712% U238, 0.06% U234

D. 99.282% U235, 0.712% U234, 0.006% U238

E. none of the above

A. boiling water reactor

B. fast breeder reactor

D. breeder reactor

E. ferrite reactor

A. there is no such unit.

C. atomic power

D. radio activity

E. voltage

A. graphite rod

B. ferrite rod

D. blanket of thorium

E. liquid sodium metal

A. reflector should be used

C. coolant should be employed

D. moderator should be used

E. control rods should be used