Recent content by zaidtaher
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Power Peaking Factor usnig MCNP5
I model the core using MCNP 5, and I want to calculate the PPF for each assembly, and I want a way to do that.- zaidtaher
- Thread
- Mcnp5 Power
- Replies: 1
- Forum: Nuclear Engineering
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MCNP Avg. Flux and Assembly Flux
I'm looking for the normalized flux for each assembly ,, please help me if there any tally like this- zaidtaher
- Post #2
- Forum: Nuclear Engineering
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MCNP Avg. Flux and Assembly Flux
I want to know the best tally for MCNP Flux (avg and for each assembly) Please help- zaidtaher
- Thread
- Assembly Flux Mcnp
- Replies: 1
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
please , I need help if u knw anyone ??- zaidtaher
- Post #16
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
But do u knw anybody can help me ? please- zaidtaher
- Post #15
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
you something I have been here for about month and I can't find what's wrong,, please help me- zaidtaher
- Post #13
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
Thanks for the file, but the problem is that the VISED didn't color all of the assemblies, and so the code will not run- zaidtaher
- Post #12
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
you just put it on VISED and will take the proper format. Regards Zaid- zaidtaher
- Post #10
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
if there a way to send the input file to you it's will be easier- zaidtaher
- Post #9
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
Dear, It didn't work either :/ Zaid- zaidtaher
- Post #8
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
I tried it, but it's already 6 spaces, but i loosed the format when I put it here, btw it's does not work Thanks for help :)- zaidtaher
- Post #6
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
1 1 -10.97 -1 -8 9 u=2 $FUEL Type 1 2 2 -0.004 1 -2 -8 9 u=2 $GAP 3 3 -6.7 2 -3 -8 9 u=2 $CLAD 4 4 -1 3 -4 5 -6 7 -8 9 u=2 $MODIRATOR 5 0 4 :-5 :6 :-7 :8 :-9 u=2 6 0 -10 11 -12 13 -8 9 fill=1 u=10 7 0 10...- zaidtaher
- Post #4
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
haha,, no I just want to see if I can have a help. the problem that I repeat a lattice but VISED didn't fill all of it in materials, and there is some red lines I don't know why.- zaidtaher
- Post #3
- Forum: Nuclear Engineering
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MCNP input file problem with AP1000 geometry
Hello Every body, I hope all is well. I have a problem with MCNP code for 1/8 AP1000, so please can anybody help me ? Regrads- zaidtaher
- Thread
- File Input Mcnp
- Replies: 15
- Forum: Nuclear Engineering