Analyzing Assumptions for Neutron Flux: Fast & Thermal Groups

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Discussion Overview

The discussion revolves around the assumptions and equations related to neutron flux in fast and thermal neutron groups, focusing on the implications of these assumptions in a theoretical context. Participants explore the relationships between neutron absorption, fission, and scattering in a nuclear physics framework.

Discussion Character

  • Technical explanation
  • Conceptual clarification
  • Debate/contested

Main Points Raised

  • One participant outlines several assumptions regarding neutron behavior, including definitions for absorption, fission, and neutron flux, as well as the categorization of fast and thermal neutrons.
  • The first equation presented is interpreted by one participant as indicating that the total neutron density of fast neutrons equals the neutrons generated by thermal fission, based on specific assumptions.
  • Another participant expresses confusion regarding the second equation, questioning why the neutron density of absorbed slow neutrons is equal to that of scattered neutrons.
  • In response to a previous post, a participant corrects a term from "boring" to "born" in relation to fission neutrons in the fast group.
  • Another participant clarifies that all neutrons created by the thermal group lead to the existence of a specific term, while correcting the previous statement about fast neutrons.

Areas of Agreement / Disagreement

Participants have not reached a consensus on the interpretation of the equations, and there are corrections and clarifications being made regarding terminology and assumptions. The discussion remains unresolved regarding the second equation and its implications.

Contextual Notes

There are potential limitations in understanding due to the assumptions made about neutron behavior, particularly regarding scattering and absorption processes. The discussion also reflects some uncertainty about the terminology used in the equations.

sandon
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Assumptions
1) a=absorption
2) f=fission
3) ∅=neutron flux
4) time independent
5) group 1, fast neutrons
6) group 2, thermal neutrons
7) All fission neutron are boring in fast group
8) All neutrons created by thermal group, thus vƩf2 exists vƩf2 does not
9) Down scattering occurs but up scattering does not, Ʃ1→2 exists, Ʃ2→1 is zero

From the prof produced 2 equations
(1) -(Ʃa1+Ʃ1→2)*∅1 + v*Ʃf2*∅2=0
(2) -Ʃa2*∅2 + Ʃ1→2*∅1=0

(1) Equation says the total neutron density of all fast neutrons(including ones scattered) is equal to the neutrons generated by thermal fission. This is correct by assumptions 7) and 8).

(2) I do not understand equation 2, why is the neutron density of the amount of slow neutrons absorbed equal to the neutron density of scattered neutrons?

Thank in advance
 
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In equilibrium (!), the number of thermal neutrons is constant. Absorption removes as many thermal neutrons as scattering produces new thermal neutrons.

7) All fission neutron are boring in fast group
I don't think "boring" is what you mean.
8) All neutrons created by thermal group, thus vƩf2 exists vƩf2 does not
Is that a typo?
 
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sorry
7) All fission neutron are born in fast group
 
8) All neutrons created by thermal group, thus vƩf2 exists vƩf1 does not
 

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