neutron spectrum

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Nikolay
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neutron spectrum

Post by Nikolay » Tue Sep 11, 2018 10:22 am

Hello. How can I specify the neutron spectrum? (I did not find the information on the forum)

Ville Valtavirta
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Re: neutron spectrum

Post by Ville Valtavirta » Tue Sep 11, 2018 6:00 pm

Could you specify what you mean?

In criticality source simulations, the neutrons are produced based on the prompt and delayed fission neutron spectra and the resulting neutron spectrum is then the product of those neutrons slowing down in the system.

For external/fixed source calculations see: http://serpent.vtt.fi/mediawiki/index.p ... inition.29

-Ville

bursar05
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Re: neutron spectrum

Post by bursar05 » Mon Sep 24, 2018 7:17 pm

Hi all,
I'm trying to obtian neutron flux energy spectrum of test reactor at the test location. I used detector card , both calculated for cell and for material. When checked detector matlab output file , the summation of mean values(which is 11. column of detector output) doesn't equal to 1. How can I find real (not relative) values of fluxes for reactor? For this, should i use 'set power' option and volume normalization 'dv' (detector) at same time?

Yrobel
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Re: neutron spectrum

Post by Yrobel » Mon Sep 24, 2018 10:32 pm

With this syntax:

Code: Select all

det NAME de 1 dt -3
you get the neutron flux per unit lethargy in the defined energy range. To define it in a location you can define the corresponding parameter (detector definition: http://serpent.vtt.fi/mediawiki/index.p ... inition.29). For example:

Code: Select all

det NAME dm MAT de 1 dt -3
. See this link for energy grid definition: http://serpent.vtt.fi/mediawiki/index.p ... inition.29. Now, to obtain the neutron flux in units (cm^-2 s^-1) you must divide the output result (DET (:, 11)) by the corresponding volume.
I hope this helps you. Regards.

bursar05
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Re: neutron spectrum

Post by bursar05 » Tue Sep 25, 2018 12:35 am

Thanks for your help Yrobel.

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