Examoogle
ExamsTest SeriesCBATRank CheckPrevious Year PapersPassBook StoreMy BooksAI Tutor
ЁЯЫТ0
рдЕA
Examoogle

India's most trusted platform for competitive exam PDF books. Expert-authored, watermark-protected, instant access.

Exams & Practice
All Exams & SyllabusMock Test SeriesPrevious Year PapersPractice Questions (MCQs)Recruitment Notifications
Quick Links
Examoogle AI TutorExam NewsBook StoreMy BooksLogin / Sign Up
Support
About UsRefund PolicyPrivacy PolicyTerms of UseContact Us
┬й 2026 Examoogle. India's #1 competitive exam AI tutor.
ЁЯФТ SSL SecuredЁЯУ▒ UPI AcceptedЁЯз╛ GST Invoice
Examoogle

Join 60,000+ competitive exam aspirants

or with email
By continuing, you agree to ourTerms of Service&Privacy Policy
Your Cart
SubtotalтВ╣0
TotalтВ╣0
Examoogle тАв User тАв info@examoogle.com тАв EE-2024-8821
Chapter 1 of 12 тАв Page 1 of 248ЁЯФТ Protected PDF тАв Watermarked
Back to Practice Questions
ElectricalPower Generation
PrevNext

What is the function of moderators in nuclear reactor?

A

Absorb the secondary neutrons

B

Slow down the secondary neutrons

C

Control the chain reaction

D

None of the mentioned

Correct Answer

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

Slow down the secondary neutrons

Quick Summary:

Moderators are materials used in nuclear reactors to slow down fast neutrons produced during nuclear fission ┬╖ By reducing the kinetic energy of these neutrons through elastic scattering, the moderator increases the probability of these neutrons being captured by fissile nuclei, thereby sustaining the chain reaction.

тЪЩя╕ПTETechnical SolutionConcept & Principle
ЁЯТб Explanation

Moderators are materials used in nuclear reactors to slow down fast neutrons produced during nuclear fission ┬╖ By reducing the kinetic energy of these neutrons through elastic scattering, the moderator increases the probability of these neutrons being captured by fissile nuclei, thereby sustaining the chain reaction.

ЁЯФв Key Formulas

╬ФE=EinitialтИТEthermal\Delta E = E_{initial} - E_{thermal}╬ФE=EinitialтАЛтИТEthermalтАЛ тАФ The energy reduction required during moderation

P=11+B2L2P = \frac{1}{1 + B^2 L^2}P=1+B2L21тАЛ тАФ Non-leakage probability influenced by moderator properties

тЪЩя╕П Working Principle

In a nuclear fission event, neutrons are emitted with high kinetic energy (approx. 2 MeV), termed 'fast neutrons'. To sustain a self-sustaining chain reaction using U235U^{235}U235, these neutrons must be 'thermalized' (slowed down to roughly 0.025 eV) ┬╖ The moderator consists of light nuclei (like Hydrogen in water or Carbon in graphite); when neutrons collide with these nuclei, they lose a fraction of their kinetic energy per collision until they reach thermal equilibrium.

ЁЯУМ Key Points
  • тЦ╕

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

  • тЦ╕

    Commonly used moderators: Ordinary water (H2OH_2OH2тАЛO), Heavy water (D2OD_2OD2тАЛO), Graphite, and Beryllium.

  • тЦ╕

    Heavy water is the most efficient moderator as it has a very low neutron absorption cross-section.

  • тЦ╕

    The process of slowing down neutrons is formally called 'Thermalization'.

тЬЕ Advantages
  • тЦ╕

    Enables the use of natural or low-enriched uranium fuel.

  • тЦ╕

    Provides safety by controlling the rate of the chain reaction.

тЭМ Disadvantages / Limitations
  • тЦ╕

    Can absorb some neutrons, reducing the neutron economy if not chosen correctly.

  • тЦ╕

    Requires additional shielding and volume in the reactor core.

ЁЯЫая╕П Applications / Uses
  • тЦ╕

    Pressurized Water Reactors (PWR)

  • тЦ╕

    Pressurized Heavy Water Reactors (PHWR)

  • тЦ╕

    Gas-Cooled Reactors (GCR)

ЁЯУД Additional Information
  • тЦ╕

    Option A is incorrect because moderators should avoid absorbing neutrons; control rods are responsible for neutron absorption.

  • тЦ╕

    Option C is incorrect because control rods, not moderators, are used for regulating the intensity of the chain reaction.

  • тЦ╕

    The ideal moderator has a high scattering cross-section (╧Гs\sigma_s╧ГsтАЛ) and a low absorption cross-section (╧Гa\sigma_a╧ГaтАЛ).

ЁЯУК Diagram / Illustration
Neutron Moderation ProcessFast NeutronsThermal NeutronsModerator
тЬЕ

B is correct тАФ Moderators are essential for slowing down fast-moving secondary neutrons to thermal energy levels to facilitate efficient fission.

Core Concepts Used
Click any tag to open in AI Tutor
Neutron Thermalization Fission Chain Reaction Nuclear Cross-sections
ЁЯТб EXAM TIP

Always distinguish between 'Moderators' (which slow neutrons) and 'Control Rods' (which absorb neutrons) to avoid common confusion in nuclear power plant questions.

Related Questions

ElectricalPower Generation
For rural and remote areas, _________________for generation and distribution is permitted
ElectricalPower Generation
With reference to EC Act-2003,Setting up State Electricity Regulatory Commission (SERC) has been made_________
ElectricalPower Generation
Which of the following generation needs permission from central electricity authority as per Electricity Act-2003?
ElectricalPower Generation
The captive generation is ________as per Electricity Act-2003
ElectricalPower Generation
As per Electricity Act-2003, The generation of electricity is

Discussion (0)

Loading discussion...
PrevNext