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Chapter 1 of 12 • Page 1 of 248🔒 Protected PDF • Watermarked
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ElectricalPower Generation
PrevNext

A moderator ______ the neutrons.

A

Accelerates

B

Slows down

C

Blocks

D

Stops

Correct Answer

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.

💡 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.

🔢 Key Formulas

E=12mv2E = \frac{1}{2}mv^2E=21​mv2 — Kinetic energy of a neutron

σf(E)∝1v\sigma_f(E) \propto \frac{1}{v}σf​(E)∝v1​ — Fission cross-section is inversely proportional to velocity for thermal neutrons

⚙️ 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.

📌 Key Points
  • ▸

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

  • ▸

    Common moderators include light water (H2OH_2OH2​O), heavy water (D2OD_2OD2​O), and graphite.

  • ▸

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

  • ▸

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

✅ Advantages
  • ▸

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

  • ▸

    Improves neutron economy by reducing non-fission capture.

❌ Disadvantages / Limitations
  • ▸

    Adds complexity to the core design.

  • ▸

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

🛠️ Applications / Uses
  • ▸

    Pressurized Water Reactors (PWR)

  • ▸

    Boiling Water Reactors (BWR)

  • ▸

    CANDU Reactors (Heavy Water)

📄 Additional Information
  • ▸

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

  • ▸

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

📊 Diagram / Illustration
Fast NeutronModeratorSlow Neutron
✅

B is correct — 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
💡 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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