A. Thorium-233

B. Plutonium-239

C. Uranium-235

A. 92

B. 235

D. 200

A. Coolant are present in different phases (e.g., heavy water and graphite)

B. None of these

C. Coolant are different materials

A. Abundant availability of water

B. Proximity to fuel source

C. Remotely located from residential areas

B. Candu reactor

C. Pressurised water reactor

D. Homogeneous reactor

A. None of these

B. Neutrons

C. ?-rays

B. Enriched uranium (3% U-235) fuelled

C. Graphite moderated

D. Homogeneous

B. Emission of hazardous radiation

C. Conversion of fissile material into fertile material

D. Velocity of the secondary neutrons

E. sing fission</strong>

A. Acts both as an efficient coolant as well as a moderator

B. Can be heated to a higher temperature without pressurizing

C. Is less prone to radiation damage

A. Has an installed capacity of 400 MW

B. Is the first power reactor in India, which became critical in 1969

D. Has two boiling water reactors of American design

A. 88

C. 52

D. 72

A. 65

B. 15

C. 45

B. Uranium oxide

C. Uranium

D. Uranium carbide

A. Second

B. Third

D. Zero

A. > 1

B. 25-Jan

C. > 200

A. Mass

B. Atomic

D. Neither A. nor B.

A. Carnotite

C. Rescolite

D. Thorium

B. Mass number

C. Number of neutrons

D. Atomic weight

B. Fermi

C. Angstrom

D. Barn

A. Require comparatively smaller pumps and heat exchanger for a given heat transfer rate

B. Is a better neutron moderator as well

D. Has a better heat transfer characteristics, and it can be pressurised to attain a high temperature

A. Have high density, but low heat transfer co-efficient

B. Be capable of attaining high temperature, only when it is pressurised

C. Be a good absorber of neutrons

A. ?-emission

B. Positron emission

C. Electron capture

A. Thermal efficiency of the former is higher

C. Maintenance cost of the former is less

D. None of these

B. Kalpakkam (Tamilnadu)

C. Kaiga (Karnataka)

D. Rawatbhata (Rajasthan)

B. He

C. N2

D. CO2

A. Liquid metal cooled

B. Swimming pool

C. Thermal

A. None of these

B. Radium

D. Plutonium

B. 4

C. 2

D. 1

A. Marine ship propulsion

C. Supplying intense fields or beams of neutron for scientific experiments

D. The production of radioisotopes

B. Breeding neutrons

C. Accelerating the neutrons

D. Accelerating the reaction rate in the core

A. Is recovered from spent fuel from thermal nuclear reactor

B. Has much lower melting point (640C ) compared to thorium (1690C)

D. Neither A. nor B.

B. Breeder

C. Power

D. Homogeneous

A. Insulation lining of the reactor

C. Lubricant

D. Fuel

A. 1/8th of it will remain intact at the end of four months

C. It will completely disintegrate in four months

D. 3/4th of it will disintegrate in two months

A. ?, ?, & ?

C. ? & ?

D. ? & ?

A. 7

C. 2

D. 1

B. Electrons

C. Nucleons

D. Protons

B. Fission products

C. Plutonium

D. Unused fuel

A. Fast breeder

B. Homogeneous

D. Highly enriched uranium (85% U-235) fuelled

B. Two

C. One

D. No

A. Plutonium-239

B. Uranium-233

C. Uranium-235

A. Ultra violet rays

C. X-rays

D. ?-rays

A. ? & ?

B. ?

C. ?

A. 10-12 cm

B. 10-24 cm

D. 1 Angstrom

A. U-233

B. U-235

C. Pu-239

A. ?-rays

B. X-rays

D. ?-rays

A. Coolant water, after being heated in the reactor core, generates steam in a boiler

B. Fuel and the coolant are thoroughly mixed to form a homogeneous solution

D. Pressurised water is pumped into the core

A. 108

B. 1012

C. 1015

B. Plutonium

C. Natural uranium

D. Thorium

A. tact with air or water</strong>

B. Cant attain high temperature at normal pressure

C. None of these

E. Is not at all corrosive, even at a higher temperature