Neutron flux of nuclear reactor

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SUMMARY

The neutron flux in a nuclear reactor is defined as the number of neutrons passing through a unit area per unit time, which is distinct from neutron current that considers the flow of neutrons. To calculate neutron flux, one typically solves the neutron diffusion equation, which describes how neutrons propagate through the reactor medium. Understanding these concepts is crucial for analyzing reactor behavior and safety. Homework questions related to neutron flux should be posted in the Engineering, Comp Sci, & Technology HW forum for appropriate guidance.

PREREQUISITES
  • Neutron diffusion equation
  • Basic nuclear reactor physics
  • Understanding of neutron flux and current
  • Familiarity with reactor safety principles
NEXT STEPS
  • Study the neutron diffusion equation in detail
  • Explore neutron transport theory
  • Learn about neutron flux measurement techniques
  • Investigate reactor safety analysis methods
USEFUL FOR

Nuclear engineering students, reactor physicists, and professionals involved in nuclear reactor design and safety assessments will benefit from this discussion.

cclkrx
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I had a homework question I am really stuck on-
How do you calculate neuron flux
 
Last edited:
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Normally one solves the neutron diffusion equation for the reactor.

What is the definition of the neutron flux, as opposed to current?


Also, homework problems need to be posted in the appropriate homework forum, which in this case would be the Engineering, Comp Sci, & Technology HW forum.
https://www.physicsforums.com/forumdisplay.php?f=158
 

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