The discussion revolves around calculating neutron flux in a finite medium using the SN method for the steady state neutron transport equation. Participants explore the implications of the calculated values, which appear to be normalized, and seek clarification on how to derive the actual neutron flux from these values.
Participants generally agree that the calculated values may not represent the real flux and that normalization is a key factor. However, there is no consensus on the exact method to derive the real flux or the specific quantities involved in the normalization process.
The discussion highlights potential limitations in understanding the relationship between normalized values and actual physical quantities, as well as the dependence on various factors such as power levels and temperature effects.
If values are going from 0 to 1 for a value, then it is probably normalized or represents a probability. Then the question is to what quantity I the value normalized. Perhaps the reaction rate or neutron production rate/density, which relates to the fission density.NukeLion said:when we calculate the neutron flux in finite medium using sn method for steady state neutron transport equation, it gives us some numbers up to 1. I am sure its not the real flux, can someone explain how we can calculte the real flux using sn method.
Correct, there would have to be some local or average (integrated) power from which to obtain a real flux. In conjunction with power and temperature (assuming some heat transfer), the temperature would have to be consistent with the resonance (doppler) broadening and moderator density.NukeLion said:Thanks Astronuc for your reply. So is it means that we need to multiply with power to get the real flux?