Gamma detectors and flux to dose

[viksap]

Thank you for prompt reply, I think its clear to me now. Using void means not just the specific material but whatever is/are there in the cell would be used.

[Ville Valtavirta]

Exactly.

-Ville

[viksap]

Hi!

Do we have something similar to PTRAC(MCNP) in Serpent?

Thank You

[Ville Valtavirta]

Not really,

do you have a specific application in mind or some specific information that you would want to extract from certain scores?

-Ville

[viksap]

Yes. Actually I want to use the particle track information for segmented detector response, where this information is crucial to correctly interpreting the intensity distribution for image reconstruction of the fuel.

Thank You

[viksap]

Hi!

How can we score the pulse height distribution of photons in two different cells in union?

Like we do in MCNP e.g. f8:p #cell1 #cell2

I am trying in this in serpent in the det card; dc #cell1 #cell2 but this gives me an error.

Shall I define the union of these two cells as one cell region in the geometry itself or there is any other way around?

Thanks & Best Regards

[Riku Tuominen]

If you don't want to modify the actual geometry, you can define a new cell that is the union of the two cells and put it into an universe that is not part of the geometry. Then use this cell in the detector with dc parameter.

[viksap]

Thank you for your suggestion, I will surely try that.