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ElectricalPower Generation
PrevNext

Which of the following material can be used as a moderator?

A

Graphite

B

Heavy water

C

Beryllium

D

Any of the above

Correct Answer

тЪЩя╕П TE тАв Technical Concept & PrincipleElectricalPower Generation
Option D

Any of the above

Quick Summary:

A moderator in a nuclear reactor is a substance used to reduce the speed of fast neutrons produced by fission, turning them into thermal neutrons ┬╖ Graphite, heavy water (D2_22тАЛO), and beryllium all possess low atomic mass and low neutron absorption cross-sections, making them effective moderators.

тЪЩя╕ПTETechnical SolutionConcept & Principle
ЁЯТб Explanation

A moderator in a nuclear reactor is a substance used to reduce the speed of fast neutrons produced by fission, turning them into thermal neutrons ┬╖ Graphite, heavy water (D2_22тАЛO), and beryllium all possess low atomic mass and low neutron absorption cross-sections, making them effective moderators.

ЁЯФв Key Formulas

╬ФE=12mv2\Delta E = \frac{1}{2} m v^2╬ФE=21тАЛmv2 тАФ kinetic energy of neutrons

╬╛=lnтБб(E1E2)\xi = \ln(\frac{E_1}{E_2})╬╛=ln(E2тАЛE1тАЛтАЛ) тАФ logarithmic energy decrement, representing average energy loss per collision

тЪЩя╕П Working Principle

The principle relies on elastic scattering ┬╖ When high-energy neutrons collide with moderator nuclei of comparable mass, they lose kinetic energy rapidly through collisions ┬╖ By reaching thermal equilibrium with the surrounding medium, these slow neutrons have a much higher probability of inducing fission in U-235 isotopes.

ЁЯУМ Key Points
  • тЦ╕

    The moderator must have a high scattering cross-section and low absorption cross-section.

  • тЦ╕

    Graphite was used in the first nuclear reactors (e.g., Chicago Pile-1).

  • тЦ╕

    Heavy water is a highly efficient moderator that allows the use of natural uranium as fuel.

  • тЦ╕

    Beryllium is effective but expensive and toxic, limiting its widespread use.

тЬЕ Advantages
  • тЦ╕

    Increases the chain reaction probability by thermalizing neutrons.

  • тЦ╕

    Allows efficient power generation using controlled fission.

тЭМ Disadvantages / Limitations
  • тЦ╕

    Materials like Beryllium are costly and difficult to manufacture.

  • тЦ╕

    Moderators occupy space within the reactor core, increasing overall size.

ЁЯЫая╕П Applications / Uses
  • тЦ╕

    Nuclear Power Generation (Pressurized Heavy Water Reactors - PHWRs).

  • тЦ╕

    Research reactors for neutron scattering experiments.

ЁЯУД Additional Information
  • тЦ╕

    Graphite was used in the Chernobyl-type reactors (RBMK).

  • тЦ╕

    Light water (H2_22тАЛO) is also a common moderator, but it absorbs neutrons, requiring enriched uranium.

ЁЯУК Diagram / Illustration
Nuclear Reactor CoreFast NeutronModeratorThermal Neutron
тЬЕ

D is correct тАФ Graphite, heavy water, and beryllium are all standard materials used as moderators in nuclear reactors to slow down fast-moving neutrons.

Core Concepts Used
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Nuclear Fission Neutron Moderation Elastic Scattering
ЁЯТб EXAM TIP

In exams, remember that a moderator must have low atomic mass to be effective; heavy elements would not absorb neutron energy efficiently through collisions.

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