CALCULATION ON SOME FISSION PRODUCTS BASED ON CONSERVATION PRINCIPLES TO EVALUATE EXISTING ENDF/B LIBRARY

Some viable summation tests derived from basic conservation principles are used to consider 20 sets of fission product yields in existing cross section library. A FORTRAN IV computer code developed at Shiraz University was used to implement these tests. Treating yield of the fission products as a probability distribution function, average quantities related to fission products can be calculated. Based on the conservation of charge, mass and nucleons at different stages after fission, important quantities such as the average number of beta decays and the average number of prompt neutrons are obtained. Calculated results for the average number of prompt neutrons are compared with available experimental data.