MCNPX Network - Open forum

Open forum of MCNPX Network

This forum serves for knowledge exchange between MCNP/MCNPX users (from beginners to experts) in addition to the restricted official mailing lists. Be aware, that information posted on this forum can be read by everyone, therefore we ask you to do not publish export-controlled, sensitive or confidential material.

The main objective of this forum is to provide a convenient way to get help on preparing input files for MCNPX and running them efficiently on desktop computers or powerful clusters. Discussions of advanced MCNPX techniques and general Monte Carlo methods are very welcome.

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Showing 1-20 of 1102 topics
copper neutron activation François Begin 2/25/15
mcnp.mpi Marina du Toit 2/25/15
mcnp6burn problem (Models required. Cannot use memory reduction option.) m joseph 2/23/15
Pu-Be Neutron Source Description (Energy) Yee Liu 2/23/15
Compiling MCNP6 Walter Rhoden 2/23/15
f5 tally Han Young Joo 2/23/15
*FMESH tally with DFn/DEn in mcnp5 (energy response function) John 2/14/15
Need Help Rosenti Pasaribu 2/11/15
[Help Needed] Unexpected neutron attenuation in Al - Doesn't make sense M 2/11/15
fatal error involving F5:p tally Rick Smith 2/11/15
hemicylindrical source on mcnpx lb 2/11/15
Running MCNP_PSTUDY with Cygwin Dylan Prevost 2/9/15
About material and cell cards Alexander Pryakhin 2/3/15
tungsten brehsstrahlung photons spectrum Cagri Yazgan 2/3/15
Neutron activation ADF 2/1/15
New to MCNP software-getting fatal errors mqsttu 1/31/15
MCNP6 rotas problem Klemen Ambrožič 1/30/15
Particles escaped wwg mesh Andrew Cannon 1/30/15
Shield Design using Weight Window Generator Erica Stone 1/30/15
xlib-unable to connect to server display zack zackzack 1/27/15
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