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• A radiation transport solver describing neutronic transport is introduced. • The model is used to reproduce shielding benchmarks included in SINBAD database. • The solver is included as a module into the high-performance computational mechanics code ALYA. • The results obtained achieved good accuracy over extended domains. • This implementation in Alya will allow coupling of radiation transport with thermo-mechanical solutions in large domains. We present significant improvements and validations of a deterministic neutron transport code (NEUTRO) dedicated to solving the Boltzmann Transport Equation. The code is integrated as a module in the Alya software package developed by the Barcelona Supercomputing Center which uses the Discrete Ordinates Method on angular coordinates, multi-group for energy discretization and FEM on unstructured meshes to treat special complex domains. The anisotropy of the scattering medium is introduced into the scattering kernel using real base expressions for spherical harmonics. In order to build the total cross-section and the respective group matrix for the elastic cross-section, we use the NJOY code. We test the solver using different geometries, orders of integration for the angular discretization and number of energy groups. Finally, we compare our results against benchmarks obtained from an NEA database that reported measurements of leakage spectra of several materials. [ABSTRACT FROM AUTHOR]

Highlights • Presentation of Alya computational mechanics code in the fusion field. • Including a neutronics module within an HPC multiphysics framework. • First benchmark results of the neutron transport module. Abstract Integrated modelling is an important element of tokamak fusion research. It contributes to the interpretation and planning of experiments, validation of theory against experimental results, development of plasma control techniques as well as the design of next step devices. Large efforts continue to be devoted to the integrated modelling of plasma physics effects in a fusion reactor core and have led to significant progress in physics understanding, while tools to model multiphysics phenomena taking place in fusion reactor components such as tritium breeding blankets have not yet reached a similar level of detail and completeness. We are developing a new high performance computing tool for simulating the latter effects. It is based a parallel computational mechanics code Alya which is specially designed for running with high efficiency standards in large scale supercomputers and is capable of solving different physics problems in a coupled way. As first step towards multiphysics simulations of fusion reactor components, we are developing a new neutron transport module based on the deterministic approach for coupling with the existing, implemented physics modules in Alya. This module, together with existing physics implemented in Alya will allow to solve future high fidelity multiphysics and multiscale problems. We present the capabilities of the Alya system and the latest version of the new neutron transport module currently under development. [ABSTRACT FROM AUTHOR]