Hi all,
I am trying to convert a set of reaction rates I have obtained from my CANDU model over different burnups to a neutrino spectrum, and I am attempting to use the Summation method to do so. In order to do this I need the beta-decay data for U-235, U-238, Pu-239, and Pu-241 along the entire fission product chain, this includes, the atomic number and mass, branching ratios of β decays to ground state (or isomeric state), and endpoint energies. Is this something I can easily grab from the current ENDF databases? Or will some additional work be required? Also, if anyone has any information on the Summation method or resources to reproduce the method I would also appreciate it greatly. Currently I am primarily following,
M. Fallot, Status of the Prediction of Reactor Anti-neutrino Spectra,
and
e. a. Th. A. Mueller, Improved predictions of reactor antineutrino spectra
But as someone new to this level of physics it’s taking some time to fully understand and replicate with just this information.
Thanks in advance for the assistance!
Jarret