hi all,
I am a biginner in OpenMC ,I made a simulation in which I used a cylindrical geometry and fixed source i I vary the radius of cylinder ,I have finds that when the radius of cylinder augmante the neutron flux decreases. what is not reel ,means that the radius of the cylinder in this case?
radius :5 Incoming Energy: 0.100000 the neutron flux : 1.91534E-02
radius :7 Incoming Energy: 0.100000 the neutron flux:3.08802E-02
radius : 10 Incoming Energy: 0.100000 the neutron flux:4.44572E-02
Even when we use three cylinder:the neutron flux in the cell increases as the radius of the cylinder augmante.
Hi Josh,
The reported flux in the tallies.out file is integrated over volume. Divide by the volume of the cylinder in each case to get the neutron flux.
-Bryan
Hello !
I have a similar question. Could you please tell what the unit of flux will be if we divide the reported flux by the volume of the cell ? Will we get [neutrons/cm^2-sec] ?
Chong
在 2014年7月7日星期一 UTC+8上午12:46:54，Bryan Herman写道：
If you are solving a fixed source problem, the units will be in neutrons / cm^2-sec IF you divide by the volume of the cell. However, you must scale this the flux by the ratio of the # neutrons per batch to the # neutrons emitted per second from your external source in your problem.