TENDL-2015

Random fission yields

Last update: 6 February 2017

Random nuclear data files can be useful to repeat identical simulations with different nuclear data. This is the whole idea behind TMC (Total Monte Carlo). For more information, please read our paper.

This collection of random fission yields are given for different incident neutron energies and isotope targets. They are produced with the GEF code (see more details about GEF here) with the help of K.H. Schmidt. Final random fission yields will ultimately be produced by K.H. Schmidt and presented on this page by the end of 2015. In the mean time, preliminary random yields are presented.

These fission yields and their uncertainties are based on the GEF code and the GEF parameters (and uncertainties). They are obtained by varying 22 model parameters. The values of the random parameters are given at the beginning of each random file. This approach has the advantage to avoid the usage of a fission yield covariance file, and to include model correlation, as in the case of the TENDL neutron cross sections. Another advantage is the consistency between random independent yields and random cumulative yields.

At the beginning of each random file, you will find the random parameters used to obtain these fission yields, as well as the averages, the standard deviations and the skewness of the random yield distributions for each random file i (these moments are calculated using all files from 0 to i).

File number 0 contains the nominal fission yields (unperturbed).

For more questions, please contact D. Rochman at PSI.