Re: Stopping Neutron in a defined region

Dear Mohammad

I think the cleanest way is performing the simulation in two steps:

1) set the phantom to BLCKHOLE and write into an external file all
particles entering the phantom, e.g., via fluscw.f that is called at each
boundary crossing, provided you define a (dummy) USRBDX for the boundary
of interest and

2) write a source routine that reads in the particles from the first step
and transports them further in the original geometry. This way you can
start the cascades in the second step with whatever particles you like.

Cheers
Stefan

On Fri, 8 Jun 2012, Mohammad Islam wrote:

> Dear FLUKA experts,
>
> Thanks for being so much helpful.
> I wanted to add few things in my previous email.
>
> I am calculating dose equivalent from neutrons produced in the snout and in the phantom. In order
> to calculate the dose equivalent from internal neutrons (neutrons produced inside the phantom), I
> need to dump the neutrons which are produced in the snout so that they can not reach the phantom.
> How can I do that?
>
> Is it possible to place a thin region of low dense material in front of the snout where all the
> neutrons produced in the upstream will be stopped (like a Bremsstrahlung electron problem
> described fluka website FAQ). I have absolutely no idea what card to use and how to do that.
> Please help me with any suggestions .
>
> Attached is my input and user routine used for Dose equivalent.
>
> Sincerely
> Mohammad Rafiqul Islam
> PhD student Oklahoma state University
> USA
>
>
Received on Sun Jun 10 2012 - 18:01:00 CEST