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 alot!
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 alot.
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?
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
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.
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...
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?