RE: Score only the primary neutron,excluding fission neutron.

Try to use for scoring in your estimator this general particles:
                        BEAMPART 210 Primary (source or beam) particles
(See also Fluka Manual page 45)

Cheers

-----Original Message-----
From: owner-fluka-discuss_at_mi.infn.it
[mailto:owner-fluka-discuss_at_mi.infn.it] On Behalf Of sugenghua
Sent: Montag, 20. Februar 2012 02:21
To: fluka-discuss_at_fluka.org
Cc: sugenghua_at_cgnpc.com.cn
Subject: Score only the primary neutron,excluding fission neutron.

Dear FLUKA experts:

       Please help me with my problem. Thanks.

       In my model, the source particle is neutron, emiting from the fuel
assembly in the middle. Water and iron surround the fuel assembly. I
want to
score the fluence of neutron in the iron.

       I want to score only the source neutron or called primary neutron,
excluding fission neutron. Namely, I don't want secondary neutron to be
transported and scored. Or, I want to switch off fission. What can I do
with
FLUKA?

       As I know, in MCNP, there is a NONU card, Fission Turnoff Card.
This
card turns off fission in a cell. The fission is then treated as simple
capture.

       The following is my thoughts, which I have tried and got no
effect.

       (1)If WHAT(6) of LOW-NEUT is 0.0,is fission neutron multiplicity
forced
to 0?

       (2)In user routines MDSTCK(management of the stack of
secondaries),
          NUMSEC is number of secondary particles produced in the
interaction,
          can I just NUMSEC=3D0?
Received on Mon Feb 20 2012 - 11:11:49 CET