Recent content by gsyou

now I use F4 card and (Fm4 -1 m -6) card to tally the power distribution. Much better than using F4 card alone. Anybody can conform that for me? Thank you!

Assume no boron and all control rods out, so the core is super-critical. if KCODE mode is used, and F4 card is for tally the neutron for each assamblies. Can the results represent the power distribution of the core, whether the multiply-factor can affect. the results i get (power...

And the error is really tricky. When I set 5000 source histories per cycle on KCODE card, the error appeared every time at source particle no. 5688, and only one inactive cycle has run. But when I set 1000 source histories per cycle, the error disappeared, and MCNP seems run well. This really...

mcnp error "the new source has overrun the old source" I am a beginner with MCNP. This error really confused me. Who knows what this error means? Thank you.

As I know, the method to solve neutron problem is divided into two steps now, neutron transport calculation for fuel assemblies and neutron diffusion calculation for whole reactor core, both using specified code such as CASMO and SIMULATE from STUSVIK. I want to know whether the commercial...

Astronuc, Thank you for your reply. So in what situation, the neutron kinetic codes need to be coupled with sub-channel TH codes, and in what situation coupled with system TH codes? Is it necessary to couple the neutron codes with all of these two kinds of TH codes together for accident...

I am quite confused for the thermal-hydraulic codes for cores and the thermal-hydraulic codes for systems. I know COBRA is a thermal-hydraulic code for cores and RELAP is a thermal-hydraulic code for systems. For the reactor transient analysis, Does it need to couple the neutron kinetics codes...