Methodology for Developing Benchmarks for Neutronic Calculations of Generation IV Reactor Characteristics

UDC: 621.039.52s

A benchmark for neutron transport simulations of fast reactors with lead coolant and mixed-nitride uranium-plutonium fuel is presented. An approach for developing adapted test problems is proposed for extending an open database of neutron transport simulation test problems with a simple and full description to widen a potential audience. The formulation of the benchmark is based on a conceptual computational model with no excessive detailing of design elements, which reduces the number of potential errors in the preparation of initial data and the model description in the tool. In addition, a methodology for developing a test problem with an equilibrium composition of nuclear fuel with a minimal reactivity margin for burnup based on existing fast reactor design concepts is described to expand the cross-verification base of fast reactors. The proposed core contains fuel in three subzones with fuel rods having different fuel column heights. This ensures a simplified core design, a negative void effect of reactivity, and effective flattening of the energy deposition distribution along the core radius. The benchmark may also be of use in an initial verification of neutron transport simulation tools for finding the errors related to the methods implemented in the tool. Comparative results of the benchmark calculations with the ENDF/B-VII.1-based data of SCALE 6.2 and the BNAB-RF data are presented, providing a reference point for the potential audience of the benchmark problem. Besides, the work highlights an educational purpose of the problem and prospects of creating a system of computational benchmarks for innovative fast nuclear reactors included in the Generation IV list.

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benchmark reactor core stepped fuel distribution fast reactor lead coolant

Link for citing the article: Tikhomirov G.V., Ternovykh M.Y., Ryzhkov A.A., Gerasimov A.S. Methodology for Developing Benchmarks for Neutronic Calculations of Generation IV Reactor Characteristics. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 1, pp. 144-159; DOI: https://doi.org/10.26583/npe.2026.1.12 (in Russian).

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