Discussion
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- Question
Which of the following may not need a control rod?
Options- A. Liquid metal cooled reactor.
- B. Fast breeder reactor.
- C. Candu reactor.
- D. None of these.
- Correct Answer
- None of these.
- 1. The mass number of an element is not changed, when it emits __________ radiations.
Options- A. ? & ?
- B. ? & ?
- C. ? & ?
- D. ?, ?, & ? Discuss
- 2. Velocity of the thermal neutron (< 0.025 eV) used for fission of U-235 is around __________ m/sec.
Options- A. 1
- B. 2200
- C. 3 x 1011
- D. 9 x 1021 Discuss
- 3. Moderating material used in a thermal-reactor should be a
Options- A. good absorber of neutrons.
- B. solid substance.
- C. poor absorber of neutrons.
- D. none of these. Discuss
- 4. Sodium melts (at atmospheric pressure) at a temperature of __________ °C.
Options- A. 58
- B. 98
- C. 348
- D. 588 Discuss
- 5. Fast breeder Test Reactor (FBTR) is located at
Options- A. Kalpakkam (near Madras).
- B. Kota (in Rajasthan).
- C. BARC (Trombay).
- D. Tarapur (in Maharashtra). Discuss
- 6. One 'amu' is equivalent to
Options- A. 9.31 MeV
- B. 931 eV
- C. 931 Mev
- D. 931J Discuss
- 7. The ratio of volume of an atom to that of its nucleus is
Options- A. 1012
- B. 10-12
- C. 10-8
- D. 108 Discuss
- 8. Which of the following is a moderating material used in nuclear reactor?
Options- A. Graphite.
- B. Cadmium.
- C. Zircalloy (an alloy of zirconium and aluminium).
- D. Stainless steel. Discuss
- 9. Which of the following is not, a fertile material?
Options- A. Th-232
- B. U-238
- C. U-233
- D. none of these Discuss
- 10. Research reactors are normally meant for
Options- A. producing high neutron flux 1012-1013 neutrons/cm2, sec and studying the effect of neutron bombardment on dif ferent materials.
- B. accelerating the neutrons.
- C. power generation.
- D. none of these Discuss
Nuclear Power Engineering problems
Search Results
Correct Answer: ? & ?
Correct Answer: 2200
Correct Answer: poor absorber of neutrons.
Correct Answer: 98
Correct Answer: Kalpakkam (near Madras).
Correct Answer: 931 Mev
Correct Answer: 1012
Correct Answer: Graphite.
Correct Answer: U-233
Correct Answer: producing high neutron flux 1012-1013 neutrons/cm2, sec and studying the effect of neutron bombardment on dif ferent materials.
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