Why is differential neutron flux commonly used in nuclear reactors?

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Discussion Overview

The discussion revolves around the use of differential neutron flux in nuclear reactors, exploring its advantages over total flux and the implications for neutron flux spectra analysis. Participants examine the context in which differential flux is preferred and mention alternative forms like integral neutron flux.

Discussion Character

  • Exploratory, Technical explanation, Debate/contested

Main Points Raised

  • One participant suggests that the choice between differential flux and total flux depends on the specific information sought.
  • Another participant notes that differential flux allows for comparison of spectra even when the energy sampling intervals differ.
  • A different participant introduces the concept of integral neutron flux and expresses interest in calculations related to it, indicating that its behavior differs from differential flux.

Areas of Agreement / Disagreement

Participants present multiple viewpoints regarding the advantages of differential flux and the relevance of integral flux, indicating that the discussion remains unresolved with competing perspectives.

Contextual Notes

Some assumptions about the definitions and applications of differential and integral neutron flux are not fully explored, and there are unresolved mathematical steps related to the calculations mentioned.

oksuz_
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Hi,

Below are the neutron flux spectra of a nuclear reactor. In the first spectrum, y-axis is differential flux and in the second spectrum, y-axis is flux (created by multiplying differential flux by energy in MeV). As far as I have seen so far, differential flux is used commonly. I am just wondering that why it is like that. Is there an advantage for using differential flux instead of just flux?

dif_flux of BP#1.png
flux of BP#1.png


Thank you.
 

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Off hand, I would say it depends on what information you are looking for.
 
Hi
It permits to compare the spectra even if the sampling (delta E) is different
PSR
 
Hello, I have seen also in some papers Integral neutron flux. I am trying to obtain it just as unfolding codes as SANDP or STAYS´L do. If somebody knows how to do that calculations I will appreciate it. The behavior in the integral neutron flux is also different from those shown previously. Thank you very much
 

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