CALCULATION METHOD OF NEUTRON EXPOSURE AGAINST INTERIOR STRUCTURE OF FAST REACTOR

摘要

PURPOSE:To obtain accurate neutron exposure in any position of interior core by combining the measurements of indcued radioactivity of neutron exposure calculation assembly provided within the core with calculated value obtained by calculation program. CONSTITUTION:Neutron flux phi at the point to solve the differential equation of formula 1 is obtained, obtaining neutron exposure by time imtegration. Neutron flux distribution and neutron exposure of pellet arranged in one axial direction are detected. Neutron exposure of any position of the inside of core may be obtained by combining the calculated value with measurements. Regarding to calculated program, the transportation calculation program is preferable to the diffusion calculation program due to solving to the outside of the core.