Modeling and analysis of depletion experiment benchmark based on assembly calculation

Abstract

[Background]Assembly calculation plays an important role in reactor core design.The depletion calculation accuracy of the assembly calculation is of great significance to the power distribution,refueling life and reactivity control design of nuclear reactor core.[Purpose]This study aims to evaluate the accuracy of the multigroup constant library in the neutron depletion calculation and establish a set of depletion experimental calculation model.[Methods]The depletion historical parameters and the final nuclide composition information were provided by the SFCOMPO-2.0 database.The information of the Takahama-3 reactor,H.B.Robinson-2 reactor and Beznau-1 reactor samples were modeled using the DRAGON code.Some simplified methods were applied to some unavailable data information.The numerical results were compared and analyzed with the benchmark results in the SFCOMPO-2.0 database.[Result&Conclusions]The results show that most of the nuclide productions are in good agreement with the reference value,and the errors are within 10%.Nuclides with large differences between numerical results and benchmark results are discussed simultaneously,and computational results of three reactor samples were compared and analyzed.