DATABASE FOR NUMERICAL SIMULATION OF FRAGMENT ACCUMULATION IN POWER REACTOR FUEL

S.N. Abramovich, V.P. Gorelov, A.A. Gorshikhin, A.N. Grebennikov, G.G. Farafontov, V.I. Il’yin
VANT. Ser.: Mat. Mod. Fiz. Proc 1996. Вып.3. С. 40-61.

      The database needed for numerical simulation of processes of binary fission fragment accumulation in power nuclear reactor fuel is discussed. The total amount of a great quantity of fragments is suggested to replace with the simplified model. Recommendations on using estimated characteristics of neutron interaction with separated fragments are given. For a great number of fission nuclear tables are presented showing yields of separated fragments, isotopes, total yields of light and heavy stable slug fragments and yields of effective light and heavy stable slug fragments. CONVERT and SUMMER programs are presented which are needed for extraction of the required values from estimated data and calculation of characteristics of neutron interaction with efficient light and heavy stable slug fragments. Algorithm implemented in SUMMER program for computation of characteristics of neutron interaction with effective fragments is given.

      Recommendations on neutron-nuclear data selection for numerical simulation of actinide nuclei accumulation in energy reactor fuel are given. ENDL-82, JENDL-3, ENDF/B-6 and BROND-2 libraries of estimated data on neutron interaction with nuclei of ^232,233Th, ^231-233Pa, ^232-239U, ^237-239Np, ^236,238,239Pu, ^241-244Am, ^242m,244mAm and ^242-249Cm are considered. RESINT program for processing data arrays corresponding to above listed libraries which was used to conduct attendant computations is presented.