2025年3月6日 · So that is a tally through the sphere, with the sphere split by surface 10. That should give two values, the integrated flux through the sphere in the region where Z is larger than 100, since the sense is positive in the FS card, and all other flux.

2024年12月3日 · Struggling with dose calculation in MCNP for brachytherapy using Ho-166. Using Fm -1 0 -5 -6 for photons results in zero, unlike F6/F8. Need help configuring F4:e,p with Fm4 to accurately calculate deposited dose for both photons and electrons.

2024年11月21日 · Question regarding the surface transform card in MCNP. I'm trying to rotate an RPP 45 degrees around the y axis (BUT NOT THE ORIGIN Y AXIS, rather the y axis at x=a, z=b). Is there a way to do this in MCNP?

2024年4月17日 · Dear all, I am a new user of MCNP, I have a problem declaring 2 sources F-18 and I-131 in 2 different cells. I only know how to declare each source for each cell, but when combining them into one declaration, I don't know how to do it. Here are my two source declarations. Please help me. Thank

2024年11月3日 · The srun is the cluster system scheduler, used to configure the number of nodes and CPUs to be used. The MCNP manual states that the command to use multiple CPUs is 'mpirun -np X', where X is the number of CPUs, followed by mcnp6.mpi (MCNP6 compiled for MPI) and input/output file parameters. I have 3 nodes, each with 16 CPUs.

2023年10月15日 · MCNP will normalise them for you. If you have say three bins that are equally likely you can just write 1 1 1 instead of 0.33333 0.33333 0.33334 and if you add a fourth bin you don't have to redo the whole lot. Some of the material card inputs can be decimal percentages and again MCNP will normalise them.

2013年11月18日 · Assume no boron and all control rods out, so the core is super-critical. if KCODE mode is used, and F4 card is for tally the neutron for each assamblies. Can the results represent the power distribution of the core, whether the multiply-factor can affect. the results i …

2019年12月14日 · A cursory glance at some of the MCNP documentation indicates to me that a dump may be available in an output file. The description in the MCNP User's Guide leads me to be a bit suspicious regarding the use of the # (complement operator) on line 38, but I haven't seen enough samples or a complete enough description to justify my suspicion as ...

2018年10月24日 · The f4 tally is probably the most obvious. The only issue is whether MCNP is able to calculate the volume of the cell on its own. In some cases, it will get a value. You should definitely verify this value, since the details of how it does it are not directly visible to you.

2023年1月9日 · Homework Statement:: PTRAC File - MCNP - Multi-core computing Relevant Equations:: No equations My name is Luiz. I am a postdoc at the institute of energy and nuclear research in São Paulo-Brazil. Our group models a cold neutron source (CNS) for the Brazilian multipurpose reactor project, through MCNP 6.2.