- (A) Heating it
- (B) Cooling it
- (C) Surrounding it by neutron reflecting material
- (D) Surrounding it by neutron absorbing material
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- (A) 9.31
- (B) 93.1
- (C) 931
- (D) 9310
- (A) β-rays
- (B) X-rays
- (C) γ-rays
- (D) Ultra violet rays
- (A) Graphite as moderator
- (B) Water as coolant
- (C) Molten sodium as coolant as well as moderator
- (D) U-235 as fuel
- (A) Neutrons
- (B) Electrons
- (C) Protons
- (D) Nucleons
- (A) Uranium
- (B) Polonium
- (C) Hafnium
- (D) Thorium
- (A) Producing high neutron flux 1012-1013 neutrons/cm2, sec and studying the effect of neutron bombardment on different materials
- (B) Accelerating the neutrons
- (C) Power generation
- (D) None of these
- (A) Power generation
- (B) Treatment of certain diseases
- (C) Initiating nuclear fission and fusion
- (D) All
- (A) U-233
- (B) U-235
- (C) Pu-239
- (D) Th-232
- (A) More than 0.71% of U-235
- (B) Only fertile material
- (C) Only fissile material
- (D) No impurities
