Mcnpx Definition and 35 Threads

This is my mcnp code: 1 4 -0.7119 1 -2 3 -4 5 -6 fill=1 imp:n=1 26 4 -0.7119 11 -12 13 -14 5 -6 u=12 lat=1 fill=13 imp:n=1 20 4 -0.7119 46 -47 -45 #1 fill=12 imp:n=1 19 0 #20 imp:n=0 3 4 -0.7119 11 -12 13 -14 u=1 lat=1 imp:n=1 fill=-4:4 -4:4 0:0 12 2r 8 9 8 12...

Hello everyone, I came across the following atom/b-cm values for a specific nuclear fuel composition: U-234.81c 1.1369e-06 U-235.81c 3.0421e-05 U-236.81c 2.4896e-06 U-238.81c 0.019613 Np-237.81c 4.6686e-05 Pu-236.81c 4.97e-10 Pu-238.81c 0.00011695 Pu-239.81c 0.0022076 Pu-240.81c 0.0013244...

Hello, What is the reason for the following error in MCNPX 2.7? Error posting readv, An existing connection was forcibly closed by the remote host. (10054)unable to read the cod header on the pmi context, Error = -1

Hello, I'm working on BURN UP analysis on a NuScale PWR with variations on U235 enrichment and the number of Gd2O3 burnable poisons rods used. I use KCODE and KSRC card as attached below. I'm having trouble with the error message on the output file. At first, I fixed that by increasing the...

Hello everyone, I'm working on a PWR fuel pin depletion simulation in MCNPX, but I'm encountering several warnings and an error that stops my simulation. Here’s my input setup: [c *** PWR pincell *** c c --- cell cards --- 1 1 -10.4 -1 imp:n=1 vol=192.29 $ fuel 2 2 -6.55 1 -2 imp:n=1...

I would like to ask about this error " bad trouble in imcn in routine dynamic allocate" this came up when I described a hexagonal fuel assembly with lat=2 fill=-17:17 -17:17 0:0 but it gave the error above. is there a maximum for this?

Hi! First of all, thank you for your time. I am simulating a nuclear engine for space applications. I want to know the fission rate of the engine but i dont know how. I am using xming to plot the fmesh 4 and the tally is: fmesh4:n geom=xyz origin= -50. -50. -50. imesh= 50...

Hello, I doing my thesis, I'm beginner in MCNPX. I want to ask about transformation in MCNPX, I want to transform this head phantom in inside and outside field ( radiation using LINAC from face to ear) in angle 90° and 270 °. Can anyone help me to solve this problem with transformation code?

When I run the application, I get an error message. Fatal error electron importances are zero, I can't find what's wrong in the code.

Hi everyone, I've been trying to analyze PTRAC output file from MCNP6 here we can see the location , cell, particle, time, and so on... My question is, I have trouble finding the unit of time listed in PTRAC, (ex, 0.30113E-02), which is hard to find in MCNP manual My intuition is that the...

Hi, All! Can anyone help me to construct a card for calculation of a spatial activation? Reaction is 27Al(n,p). I used a tmesh card for calculation of neutron flux as: tmesh rmesh21:n flux cora21 190 9i 210 corb21 -10 9i 10 corc21 -10 9i 10 ergsh21 0 20 endmd Somewhere in a problem I...

I get this error"bad trouble in imcn in routine pass1 unexpected eof in file depletion.inp" when I try to run the code MCNPX my input file c Depletion pincell input file for MCNPX c Define cells c Cell 1: Fuel 1 0 -1.0 -4 -5 -6 c Cell 2: Cladding 2 0 -2.0 4 -7 c Cell 3: Moderator 3 0 -3.0...

Hello - what is an accepted definition of the skyshinne dose in MCNP and how would you calculate this? If you have a source and a shield a few meters away between the dose point, the contribution that goes around the shield would be skyshine....but..what if you have a big source region (e.g., a...

When I run the application, I get an error message. This message: Fatal error too many numbers first entry. What could be the reason?

Hello everyone! We get Problem to run Moritz on a given PC when its works on others PCs What could be the solution in fact , we can see the exe running in the taskmanager but not GUI is opened.. Thanks in advance for help Thibaut

I know that "mcnpx n=filename" I run the file, but how do I run the entire folder with the entries inside?

Hi there I want to convert the flux (F4:N tally) from mcnp units to cm-2s-1 units. How to do that? Also I have some bug in MCNPX: while running the file, I get an error like " >bad trouble in imcn in routine xin >Cannot find bertin " How to solve it? Database for MCNP5-MCNPX got installed already.

Homework Statement:: I go back to the line to finish the previous line in MCNP cell card but I had the error message shown in the photo. Please make a solution to my problem Relevant Equations:: c ********************* BLOCK 1: cartes des cellules **************** 1 2 -1.184 -40 #3 #19 #18...

Hi, I am interested in simulation of parallel beams for neutrons and photons (separately of course). Any ideas on how to simulate them in MCNP5 or MCNPX?

Hey there, I'm working on an MCNPX modelling for SCWR using different clads and fuels, the first fuel was UO2(5%) and I have calculated the number density correctly since there was only one vector U. But now I don't know how top deal with the Th+U233 due to the existence of Thorium. Can anyone...

Hello,guys, I wonder how to use mesh tally to calculate dose.I set a cylinder，and set the material of the cylinder.Then I want to divide a cylinder into smaller cylinders in a direction perpendicular to the z-axis.And I need to record the flux of each mesh,use dedf card to get dose. I have tried...

My MCNPX is not working when I start the calculation. It says "bad trouble in imcn in routine xin cross-section file bertin does not exist."

Why does mcnpx not recognize the shell when I crop the cell in half? I put on a lead shield. I put everything (covering everything) and it worked. I cut half and the shield stop of work, but the cell is there. 10 2 -0.9500 (-1 2 -3) #20 imp:p=1 VOL=149.2256511 $ espessura / thickness...

My code version is 2.7 I have a disk source of R=0.3 cm, 60 cm above in z axis. I want set limits for the x and y axis, but, I can only put one command "axs" and "ext". How can i define two limits with one command? my code it is like this SDEF pos=0 0 60 rad=d1 axs=1 0 0 ext=d2 PAR=2 ERG=0.018...

Hi, my name is alexander, i am student from Institute of radioprotection and dosimetry (IRD). My project is calculate MGD (mean glandular dose) from womans with augmented breast. i am having dificulties to calculate Kerma in air with mcnpx. I drew a block of air above the breast, i am using the...

Designing a PWR core in MCNPX for burnup using 4 folds rotational symmetry to reduce computational time of the core, taking reflective boundary conditions on rotational symmetry planes. should the power be reduced to 1/4th of original power (3000 MWth) in burnup card or does the reflective...

Hi, I would like to know if there is any maximum limit for number of particle histories can be used in mcnpx input file. Thank you. Regards,

Hello everyone! I would like to ask you if anyone can help me solving my Problem with mcnpx. I created a file with a watertank, a nozzle and a slit blend on the surface. I also inserted a protonbeam and would like to plot the dose and fluence for examplte with Moritz. But when I execute the...

Hello, i am Ali doing PhD studies i am working on Activation Analysis of Hybrid reactor but i just stat studying this geometry but i am not able to understand this geometry for MCNPX modeling, so i need some help in modelling this geometry in MCNPX. please guide me in this regard

I got and fatal error like below. " fatal error. continue run not yet consistent with histp writing. " Couldn't I use continue run when I make histp file? please, help me... calculation time is too long, so I want to use continue run.

Hello everyone, I need help. Anyone can explain what is the basic differences between MCNP5 and MCNPX? I appreciate every suggestion for help me. Thanks. Rose

I am running a simple MCNPX input code and am getting a fatal error that says: "Fatal Error: no m card for material no. X". I thought it was something with my data card or my cell cards but can not figure out what the problem is.

hi please help me to download free MCNPX Or MCNP5C ! Where can i download those soft? Or MCNPX visual basic? please help me! tanx

Hi there any body know that mcnpx has abality to do time dependent calculations? please lead me quickly, I need it. regards