According to my knowledge, MCNP is using (as most of the MC calculation codes) the power iteration method, as explained in the following document: https://mcnp.lanl.gov/pdf_files/la-ur-06-7094.pdf
In particular, this method is detailed after page 14.
As a consequence, my question is well defined...
Dear community,
I am trying to construct the decay chains and the decay radiations from ENSDF files. Until now, I have used the ones included in the ENDF6 file format such as JEFF3 or ENDFBVIII etc... However, I have been told that ENSDF was especially done for decay data.
I found the software...
Thank you Astronuc for your reply and sorry for the time I took to answer.
Using the power iteration algorithm, I compute the k-eigenvalue. It s a mathematical method that permits to compute the eingenvalue and the associated eigenvector (the flux) by iterations, just like it is done within...
Dear Community,
I am having a question. I have developed a simple code to perform iteration power algorithm and find the keff value of a system. However, it is not still totally clear in my mind if I have to normalize all my scores by the eigenvalue, i.e. multiply by the keff (fluxes, power...
Hi everybody,
I am trying to score fission spectrum in MCNP for a kcode calculation. I would like to check at which energy neutrons produced by fission are generated. I have no idea how to perform since tallies are usually volume or material dependent and I just want to build a spectrum...