Calculation of the pin power distribution for a thorium reactor assembly and benchmarking
Affiliation:
1. National Center for Nuclear Safety, Atomic Energy Authority, 3 Ahmed Alzomer Street, P.O.Box 7551, Cairo, Egypt. Email:
Abstract
Abstract
A computer model was developed to perform neutronic and burn-up analysis for an assembly of a thorium reactor. The MCNP computer code was used to model the geometry of the assembly and to determine both, the power and flux distribution. A system of ordinary differential equations which represents all fuel isotopes was solved numerically to evaluate the time behavior of fuel composition and burn-up. The results of the present model were compared with the solutions of benchmark problems and satisfactory agreement was found.
Publisher
Walter de Gruyter GmbH
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation