Nuclear Reaction Empire Model Program Development And N + ~ (58,60,61,62,64) Ni Model

The goal of this work is to introduce the EMPIRE code system to Chinese Evaluated Nuclear Data Library (CENDL) of China Nuclear Data Center (CNDC) where a series of nuclear reaction model codes, MUP, UNF, APMN et al, have been developed and a lot of nuclear data evaluations have been done by these codes. It is expected that the improvement of CENDL will be achieved in nuclear reaction model code system and evaluation method by this work. With this new code system, theoretical model calculations for n+^{58,60,61,62,64} Ni reactions have been performed.The EMPIRE code system was developed by Mike.Herman in 1982 and has been widely used in ENDF/B-VII. Many mature nuclear reaction models, optical model, Coupling Channels, DWBA, Multi-step Direct (TUL), Multi-step Compound (NVWY), Exciton model and Hauser-Feshbach model, were involved in the EMPIRE code system which can be used for the projectile of any nucleon or heavy ions with a very broad energy region (0-200 MeV). Besides, the EMPIRE code system provided many benefits such as the convenient connection with RIPL and EXFOR, the friendly interface and the short run time.Based on experimental data of total reaction cross sections, elastic scattering cross sections and elastic scattering angular distributions of n+Ni and its isotopic nuclears, the detail calculations and analyses were performed on all cross sections of neutron induced reaction, the elastic scattering angular distributions, the cross sections and inelastic scattering angular distributions of discrete levels, double differential cross sections of neutrons emission as well as neutron energy spectrum by using a set of suitable neutron optical potential and related parameters selected from the Reference Input Parameter Library-2 (RIPL-2) in the region of incident neutron energy below 20MeV. The calculated results of present work are not only compared with the experimental data but also compared with other evaluated data from ENDF-BVII, JENDL-3.3, JEFF-3.1 and CENDL-3.0. It shows that the present results are reasonable and agree well with experimental measurements, especially in double differential cross sections of neutrons emission.