MCNP: Integral flux crossing the spherical surface of a spherical cap
2025年3月6日 · TL;DR Summary I want to calculate the integral flux crossing the spherical surface of a spherical cap, which I have defined using a spherical surface and a plane. What tally should I use?
Help with F4 Fm4 dose calculation in MCNP simulation
2024年12月3日 · TL;DR Summary 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.
MCNP TR Transform Card Question - Physics Forums
2024年11月21日 · TL;DR Summary Question regarding the surface transform card in MCNP.
MCNP: Declaring two sources in two cells - Physics Forums
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...
Question about multiple runtimes on MPI for MCNP6
2024年11月3日 · 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.
Question about Source Probability in MCNP - Physics Forums
2023年10月15日 · Here, SP stands for source probability. But probability needs to be normalized. Here values in SP3, SP4 are larger than 1, It means that SP is not ordinary probability here. But what actually SP represent here?
"Unexpected error in file" in MCNP - Physics Forums
2019年12月14日 · Hello, I am getting the following error Unexpected error in file I have gone through the code and noting seems to be amiss. Does anyone have any ideas?
How to use MCNP to calculate power distribution for a reactor core?
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 …
Use of tally with surfaces and macrobodies in MCNP
2018年10月24日 · Hi. I need some help with the use of tally card in MCNP. I have been trying to use the f1, f4 and f2 tally to calculate surface current, average flux on a cell and avergage flux on a surface respectively, my question is: It's possible use …
PTRAC File - MCNP - Multi-core computing - Physics Forums
2023年1月9日 · Our group models a cold neutron source (CNS) for the Brazilian multipurpose reactor project, through MCNP 6.2. We need a PTRAC file in the CNS region and would like to know if it is possible to obtain this file through multi-core computing.