Recent content by chivasorn
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Hi,I want to know about SIMULATE code. how can I get its
Hi, I want to know about SIMULATE code. how can I get its manual? thanks a lot- chivasorn
- Thread
- Code
- Replies: 1
- Forum: Nuclear Engineering
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Calculating Group Constants for FA with MCNP
hi there I wnat to calculate the group constants for a FA(fuel assembly) using MCNP (similar to lattice calculations). How can I do it? Please lead me. Thanks a lot!- chivasorn
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- Constants Group Mcnp
- Replies: 1
- Forum: Nuclear Engineering
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How to Calculate C Parameter in FMn Card for MCNP Code
Hi there I have a question about FMn card in mcnp code. there is a parameter (is named C) in front of FMn card, I can not understand to calculate the value of that parameter. please help me. thanks a lot.- chivasorn
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- Code Mcnp
- Replies: 2
- Forum: Nuclear Engineering
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What is a Supercritical Water Reactor?
thanks Astronuc, can you explain about neutronic calculations and the used codes for SCWR? Whether the existing codes can be used for this type of reactor is?- chivasorn
- Post #3
- Forum: Nuclear Engineering
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What is a Supercritical Water Reactor?
Hi there, I want to know about SCWR(supercritical water reactor) that is a Gen IV reactor. Has anybody introduce the technology of SCWR & SSCWR. thanks- chivasorn
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- Reactor Water
- Replies: 6
- Forum: Nuclear Engineering
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Can MCNPX Perform Time Dependent Calculations?
Hi there any body know that mcnpx has abality to do time dependent calculations? please lead me quickly, I need it. regards- chivasorn
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- Mcnp Mcnpx Time Time dependent
- Replies: 1
- Forum: Nuclear Engineering
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Temperature in MCNP - Using Library ENDF7 for Research Reactor
Hi Astronuc. I have another question; TMP card in MCNP that can be entered at cell card have not any effect in result of calculations? Please, more explain about that, I need. have best time.- chivasorn
- Post #3
- Forum: Nuclear Engineering
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Temperature in MCNP - Using Library ENDF7 for Research Reactor
Hi there, I want to know that how can involve the temperature in mcnp code. for example; the library endf7 for mcnp has five certain temperature:300 kelvin, 600 kelvin, 900 kelvin, 1200 kelvin & 1500 kelvin. if I want to calculate flux distribution in 330 kelvin for a research reactor, how can...- chivasorn
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- Mcnp Temperature
- Replies: 5
- Forum: Nuclear Engineering
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Why Does Fission Chamber React to Neutron Fluxes Over Source Range?
why does fission chamber start to work from neutron fluxes more than source range in spite of being a kind of ionization chamber that is sensitive to gamma rays?- chivasorn
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- Chamber Fission Neutron Range Source
- Replies: 3
- Forum: Nuclear Engineering
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Using HELIOS Code for Preparing Macroscopic XS in PARCS
Thank you Astronuc!- chivasorn
- Post #5
- Forum: Nuclear Engineering
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Using HELIOS Code for Preparing Macroscopic XS in PARCS
Hi Astronuc Do you know how can I obtain HELIOS code? because I need that in order to link to PARCS.- chivasorn
- Post #3
- Forum: Nuclear Engineering
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Control Rod Worth: Power Dependency?
Thanks Astronuc. Your response is very useful.- chivasorn
- Post #5
- Forum: Nuclear Engineering
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Control Rod Worth: Power Dependency?
thank thecandyman.- chivasorn
- Post #3
- Forum: Nuclear Engineering
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Using HELIOS Code for Preparing Macroscopic XS in PARCS
Hello all Has anybody use HELIOS code yet? I need that in order to preparing macroscopic XS to PARCS.- chivasorn
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- Code Macroscopic
- Replies: 5
- Forum: Nuclear Engineering
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Coupling between neutronic and thermalhydraulic codes
Hi Libertad I have a peresentation(ppt) about coupling neutronic & thrmohydrolic codes(wims+citation+cobra). But I have not your mail to sending you.- chivasorn
- Post #4
- Forum: Nuclear Engineering