JENDL-3.2 / file 315 (fission product yields)

File 315 is only for the ENDF-6 format version. In the ENDF-5 format, the fission product yields are given together with cross section data of fissioning nuclei.

                                                   
 
          NUCLIDE      MAT  RECORDS           
    1    90-TH-232    9040   3313             
    2    92-U -233    9222   4948             
    3    92-U -235    9228   4948             
    4    92-U -236    9231   1673                 
    5    92-U -238    9237   3312             
    6    93-NP-237    9346   1673             
    7    94-PU-239    9437   4948             
    8    94-PU-240    9440   1672             
    9    94-PU-241    9443   3310             
   10    94-PU-242    9446   1672            
   11    95-AM-241    9543     69             
   12    95-AM-243    9549     69            
                TOTAL =     31607 RECORDS