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- Help with F4 Fm4 dose calculation in MCNP simulation
Hello everyone, I am facing difficulties while trying to calculate the dose in the tibia due to brachytherapy in an MCNP simulation We are working with the radionuclide Ho-166, and therefore, we need to account for both photon and electron contributions to the deposited dose Initially, I
- MCNP4 help: f4 tally in lattice • Physics Forums
F4 is a flux tally, but instead of counting the neutrons going through it MCNP measures the total path length and divides it by the volume of the cell to calculate the flux
- Understanding MCNP Tally F5 Output: Tips for Beginners
I am beginner in MCNP Could someone please show me how to read the output file when using Tally F5 I saw that the result involves collided and uncollided photon flux, so which part needs to be chosen for calculating? Thank you
- MCNP: Declaring two sources in two cells • Physics Forums
A new user of MCNP is seeking assistance in declaring two sources, F-18 and I-131, in different cells It is suggested that performing separate runs for each source may simplify the process and help identify errors The discussion includes technical details on how to extend source definitions and dependent variables for the simulation Additionally, the user mentions challenges with liquid
- [MCNP6] How to use Tally E with Fmesh • Physics Forums
Hello everyone, I do need your help in this matter, please kindly help me solve this problem I use MCNP5 and i want to use Tally E with Fmesh I use Tally E and Fmesh this way with MCNP5 F4:P,E 6 E4 0 200i 2 FMESH4:P GEOM=REC ORIGIN=-550 -550 -1 IMESH=-50 IINTS=5 JMESH=550
- MCNP: Integral flux crossing the spherical surface of a spherical cap
TL;DR 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?
- MCNP FMESH for Plotting power distribution • Physics Forums
Hello I'm trying to use FMESH command to get power distribution of this core geometry I want to use xyz coordinate in a 1 12 slice of a core so I could use the output of the MCNP sim for a CFD input How should I approach this? Thank you
- Specifying temperatures in MCNP • Physics Forums
To specify temperatures in MCNP, convert the temperature in Kelvin to MeV using the Boltzmann constant (8 617e-11 MeV K) For instance, a fuel temperature of 500K translates to "tmp=4 30185E-08" Additionally, ensure that the material cards reference the correct temperature libraries, which have been moved from the user manual to a separate document Users should also verify the appropriate S
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