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Related Concept Videos

Nuclear Power02:36

Nuclear Power

Controlled nuclear fission reactions are used to generate electricity. Any nuclear reactor that produces power via the fission of uranium or plutonium by bombardment with neutrons has six components: nuclear fuel consisting of fissionable material, a nuclear moderator, a neutron source, control rods, reactor coolant, and a shield and containment system.
Nuclear Fuels
Nuclear fuel consists of a fissile isotope, such as uranium-235, which must be present in sufficient quantity to provide a...

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Fabrication of Gate-tunable Graphene Devices for Scanning Tunneling Microscopy Studies with Coulomb Impurities
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Graphite moderated (252)Cf source.

Laszlo Sajo-Bohus1, Haydn Barros1, Eduardo D Greaves1

  • 1Universidad Simón Bolívar, Nuclear Physics Laboratory, Apdo 89000, Caracas 1080A, Venezuela.

Applied Radiation and Isotopes : Including Data, Instrumentation and Methods for Use in Agriculture, Industry and Medicine
|March 16, 2015
PubMed
Summary
This summary is machine-generated.

A subcritical thorium reactor project aims to train personnel. Researchers simulated neutron spectra and dose equivalents using a Californium-252 source and MCNP5 code for reactor development.

Keywords:
(252)CfAmbient dose equivalentMonte CarloNeutrons

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Area of Science:

  • Nuclear Engineering
  • Reactor Physics
  • Materials Science

Background:

  • Thorium molten-salt reactors offer an affordable nuclear power solution for developing nations.
  • A project at Universidad Simon Bolivar focuses on developing a subcritical thorium liquid-fuel reactor for training and experience.
  • The reactor design utilizes a Californium-252 neutron source and high-purity graphite as a moderator.

Purpose of the Study:

  • To estimate the neutron spectra of Californium-252 within the graphite moderator.
  • To determine the ambient dose equivalent surrounding the moderator.
  • To support the development of a subcritical thorium liquid-fuel reactor for educational purposes.

Main Methods:

  • Neutron transport simulations were performed using the MCNP5 code.
  • The neutron spectra were calculated at the center of the graphite moderator, along the liquid thorium salt channel.
  • Ambient dose equivalent was determined using MCNP5 simulations.

Main Results:

  • The neutron spectra of Californium-252 were successfully estimated within the graphite moderator.
  • The ambient dose equivalent around the moderator was calculated.
  • Simulation data provides crucial information for the subcritical reactor design.

Conclusions:

  • The simulation results provide essential data for the ongoing development of the subcritical thorium liquid-fuel reactor.
  • This project contributes to personnel training and practical experience in nuclear reactor technology.
  • The findings support the feasibility of using Californium-252 as a neutron source in this reactor design.