Validations of the radiation transport module NEUTRO: A deterministic solver for the neutron transport equation

Soba, Alejandro; Cazado, Mauricio E.; Houzeaux, Guillaume; Gutierrez-Milla, Albert; Mantsinen, M.; Sáez, X.

doi:10.1016/j.fusengdes.2021.112497

Cited by 1 publication

(5 citation statements)

References 27 publications

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“…This allows us to evaluate both the angular and the mirror direction for each reflective boundary of the domain at the beginning of the simulation. Further details of the numerical methods applied in the code to solve the Boltzmann transport equation can be found in [2].…”

Section: Numerical Radiation Transport Equationmentioning

confidence: 99%

“…These cases were simulated using unstructured meshes comprised of linear tetrahedra, using 59 groups to divide the energy spectrum. An angular discretization using discontinuous finite elements called FE64 was applied, which was described in previous works [2]. In figure 6 we have plotted a summary of seven of the cases studied with NEUTRO, comparing the numerical results for leakage with the measured data.…”

Section: Sinbad Testingmentioning

confidence: 99%

“…These challenges become manageable as our software is included within the Alya system. Furthermore, the good scalability of the Alya system in coupled multiphysics problems will help us achieve high performance in large-scale calculations [2,6].…”

Section: Numerical Radiation Transport Equationmentioning

confidence: 99%

“…The main purpose of these benchmarks was to study the neutron and gamma-ray leakage spectra from the outer surface of the spheres. Parts of these results have been discussed previously [2] and we included here an exhaustive set of the simulations performed. As an example, Figure 5 presents the comparison between experimental data and calculated leakage values for a silicon sphere of 40 cm in diameter.…”

Section: Sinbad Testingmentioning

confidence: 99%

“…This paper presents the current status of the deterministic neutron transport code NEUTRO, dedicated to solving the Boltzmann transport equation [2], developed as one of the physics modules in the massively parallel finite element general software package Alya [3][4][5]. Alya is a framework created to solve different physical phenomena in a coupled way, in large scale supercomputers, accomplishing scalability and high parallelism standards.…”

Section: Introductionmentioning

confidence: 99%

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Validating NEUTRO, a deterministic finite element neutron transport solver for fusion applications, with literature tests, experimental benchmarks and other neutronic codes

Goldberg¹,

Duxans²,

Gelabert³

et al. 2022

Plasma Phys. Control. Fusion

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Neutron reactions on fusion reactor materials are key phenomena to be understood to enable fusion as a feasible energy source for future reactors. We present significant improvements and validations of NEUTRO, a deterministic neutron transport code dedicated to solving the Boltzmann Transport Equation. The code is integrated as a module in the Alya system developed by the Barcelona Supercomputing Center and uses the Discrete Ordinates Method over an angular portion, multigroup for energy discretization and the Finite Element Method over unstructured meshes to treat special complex domains. Material 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 and materials with varying levels of scattering properties. We compare our results on classic tests, benchmarks obtained from a Nuclear Energy Agency database and test cases using other neutron transport codes.

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Section: Numerical Radiation Transport Equationmentioning

confidence: 99%

Section: Sinbad Testingmentioning

confidence: 99%

Section: Numerical Radiation Transport Equationmentioning

confidence: 99%

Section: Sinbad Testingmentioning

confidence: 99%