METHOD FOR EVALUATING BEHAVIOR OF NEUTRON FLUX IN NUCLEAR REACTOR

摘要

PPROBLEM TO BE SOLVED: To obtain a method for evaluating behavior of neutron flux in a reactor capable of improving the convergence of iterative computation in the case of numerically calculating a second order partial differential equation for neutron flux by using a response matrix method and drastically shortening computing time. PSOLUTION: When the second order partial differential equation expressing the neutron flux is solved by the response matrix method in the evaluation method for behavior of neutron flux in a reactor for evaluating neutron flux determined by the shape and composition of a reactor core by repeating calculations of m-th predication of the second order partial differential equation expressing the behavior of neutron flux and converging until the m-th predication and m+1th predication get sufficiently close, and obtaining an approximated value, a partial differential equation improved in convergence of iterative computation by multiplying neutron macroscopic cross section given as an input by a scaling constant is used. PCOPYRIGHT: (C)2004,JPO