A. does not absorb neutrons
B. absorbs neutrons
C. accelerates neutrons
D. eats up neutrons
E. regenerates neutrons
Related Mcqs:
- Gas cooled reactor uses following materials as moderator, and coolant____________________?
A. graphite, C02
B. graphite, air
C. heavy water, C02
D. lead, H2
E. concrete, N2 - Boiling water reactor uses the following as moderator, coolant and working fluid________________?
A. ordinary fluid
B. heavy water
C. molten lead
D. hydrogen gas
E. none of the above - Moderator in nuclear plants is used to__________________?
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 - The most commonly used moderator in nuclear plants is___________________?
A. heavy water
B. concrete and bricks
C. graphite and concrete
D. deutrium
E. graphite - In boiling water reactor, moderator is__________________?
A. coolant itself
B. ferrite rod
C. graphite rod
D. liquid sodium metal
E. blanket of thorium - The fast breeder reactor uses the following moderator__________________?
A. demineralised water
B. carbon dioxide
C. heavy water
D. graphite
E. no moderator is used - The risk of radioactive hazard is greatest in the turbine with following reactor___________________?
A. pressurised water
B. boiling water
C. gas cooled
D. liquid metal cooled
E. all of the above. - A pressurised water reactor employs pressuriser for the following application________________?
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 - In triggering fission, the following types of neutrons are desirable_________________?
A. fast moving
B. slow moving
C. critical neutrons
D. neutrons at rest
E. none of the above - Each fission of U235 produces following number of fast neutrons per fission________________?
A. 1 neutron
B. 1 — neutrons
C. 1 – 2 neutrons
D. 2 — neutrons
E. infinite