Burn-up (MCNPX Manual Page: 5-77)dongge said:Hi for everyone, anyone knows whether it is possible to execute burnup process in MCNP5? I want to get K-inf as fuel depletion goes on. Thanks
http://homepages.cae.wisc.edu/~bohm/neep412/lucasMCNPTutorialspring2010.pdfBurn-up of the fuel is one of the most important aspects for determining economic output of the reactor,
and could be a driving factor in the design of some of the new reactors that have to be run in remote areas
for 10+ years without a refueling. These constraints of the project are heavily emphasized in the initial design
phase and the final phase of gathering results, but burn-up does not play a large role in the central design portion
of the project. For this reason I have included burn-up as the last thing to cover in this tutorial. By this
point you should have a fully working model and realize what all of the information you are getting out pertains
too. The burn card can only be implemented with MCNPX, and is not in MCNP5.
thanks a lot. and I am going to try mcnpx and mcode.:DAstronuc said:Burn-up (MCNPX Manual Page: 5-77)
http://homepages.cae.wisc.edu/~bohm/neep412/lucasMCNPTutorialspring2010.pdf
It's not clear to me, but perhaps BURNCAL can be used for depletion calculations with MCNP5. There are numerous examples of coupled codes in nuclear R&D/industry.
http://prod.sandia.gov/techlib/access-control.cgi/2002/023868.pdf
Here is another example of coupling MCNP with ORIGEN in a code called MCODE.
http://dspace.mit.edu/bitstream/handle/1721.1/16603/55011734.pdf?sequence=1