Research on methods for distribution of neutron flux in the experiment target

ANISN is chosen as the program for the calculation of distribution of neutron flux in the experiment target in the light of future experiment trait. A program is developed to make the data describing mixed material. The neutron flux data near external frame and delayed tank in the reactor have been calculated. After comparing with the data measured, it can be said that those data calculated are believable. The factors of self shield of the target flakes have been calculated. After comparing with the data measured, it is thought that those factors calculated are believable. The distribution of flux data in the target got by calculated are the theoretical basis of the future experiment. (authors)