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ElectricalPower Generation
PrevNext

A moderator ______ the neutrons.

A

Accelerates

B

Slows down

C

Blocks

D

Stops

Correct Answer

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

Slows down

Quick Summary:

A moderator is a material in a nuclear reactor that reduces the kinetic energy of high-speed (fast) neutrons to lower (thermal) energy levels ┬╖ By slowing these neutrons down, the moderator significantly increases the probability of fission occurring in U-235 fuel.

тЪЩя╕ПTETechnical SolutionConcept & Principle
ЁЯТб Explanation

A moderator is a material in a nuclear reactor that reduces the kinetic energy of high-speed (fast) neutrons to lower (thermal) energy levels ┬╖ By slowing these neutrons down, the moderator significantly increases the probability of fission occurring in U-235 fuel.

ЁЯФв Key Formulas

E=12mv2E = \frac{1}{2}mv^2E=21тАЛmv2 тАФ Kinetic energy of a neutron

╧Гf(E)тИЭ1v\sigma_f(E) \propto \frac{1}{v}╧ГfтАЛ(E)тИЭv1тАЛ тАФ Fission cross-section is inversely proportional to velocity for thermal neutrons

тЪЩя╕П Working Principle

Fast neutrons produced during fission move at very high speeds and are likely to escape the fuel or be captured by U-238 without causing fission ┬╖ The moderator consists of light nuclei (like Hydrogen in water or Carbon in graphite); when neutrons collide elastically with these nuclei, they transfer a fraction of their kinetic energy, effectively slowing them down until they reach thermal equilibrium with the surroundings.

ЁЯУМ Key Points
  • тЦ╕

    Thermal neutrons have much higher fission cross-sections than fast neutrons.

  • тЦ╕

    Common moderators include light water (H2OH_2OH2тАЛO), heavy water (D2OD_2OD2тАЛO), and graphite.

  • тЦ╕

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

  • тЦ╕

    If neutrons are not slowed down, a self-sustaining chain reaction is difficult to achieve in thermal reactors.

тЬЕ Advantages
  • тЦ╕

    Enables chain reaction with natural or low-enriched uranium fuel.

  • тЦ╕

    Improves neutron economy by reducing non-fission capture.

тЭМ Disadvantages / Limitations
  • тЦ╕

    Adds complexity to the core design.

  • тЦ╕

    Moderators like graphite can pose fire risks; water requires high-pressure vessels.

ЁЯЫая╕П Applications / Uses
  • тЦ╕

    Pressurized Water Reactors (PWR)

  • тЦ╕

    Boiling Water Reactors (BWR)

  • тЦ╕

    CANDUReactors (Heavy Water)

ЁЯУД Additional Information
  • тЦ╕

    Fast neutrons typically have energies around 1-2 MeV, while thermal neutrons are around 0.025 eV.

  • тЦ╕

    Option B is the correct choice because the primary function of a moderator is to maximize collision probability through kinetic energy reduction.

ЁЯУК Diagram / Illustration
Fast NeutronModeratorSlow Neutron
тЬЕ

B is correct тАФ A moderator slows down high-energy neutrons to thermal energies to sustain the nuclear chain reaction.

Core Concepts Used
Click any tag to open in AI Tutor
Nuclear Fission Neutron Thermalization Moderation Ratio Cross-section
ЁЯТб EXAM TIP

Remember that while a moderator slows neutrons, a control rod (like Boron or Cadmium) absorbs them to stop the reaction ┬╖ Do not confuse these two functions.

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