Nodal SN-method for HEX-Z geometry

Acceleration performance results of the SN nodal transport solvers in MOSASAUR code system for lead-based reactor cores

“…Existing fast reactor physical analysis codes mostly adopt PN/SPN variational nodal method (VNM) and SN nodal method (SNM) for reactor core transport calculation. For example, the US fast reactor analysis code DIF3D adopts the DIF3D-VARIANT (Smith et al, 2014) solver based on the PN/SPN SNM (Zhang and Li, 2022), the French fast reactor analysis system ERANOS adopts the TGV/VARIANT (Ruggieri et al, 2006) solver based on the PN/SPN VNM, Japan and Russia have developed NSHEX (Todorova et al, 2004) and CORNER (Bereznev, 2016) codes based on SNM with hexagonalprism mesh for fast reactor physics analysis. And the fast reactor analysis codes of XJTU (Zheng et al, 2018) and NPIC (Zhang et al, 2023) have adopted the SNM based on triangular-prism, hexagonalprism, and quadrangular-prism meshes.…”

“…The SN nodal method mentioned here is derived from the earlier discrete nodal transport method (DNTM) (Lawrence, 1986). It has been extended to hexagonal-prism (Todorova et al, 2004;Bereznev, 2016;Xu et al, 2020) and triangular-prism (Lu and Wu, 2007) meshes and has been applied and developed in several fast reactor analysis codes. Starting from the multigroup neutron transport equation, SNM discretizes angle variables of the neutron transport equation by the discrete-ordinates (SN) method and discretizes spatial variables with coarse meshes.…”

Simulación multi-física y multi-escala de un reactor nuclear enfriado con metales líquidos

“…Los modelos nodales resuelven la ecuación de difusión tridimensional en geometrías cartesianas y / o hexagonales usando las secciones eficaces homogeneizadas. Los códigos nodales usados con más frecuencia para las aplicaciones de reactores rápidos son DIF3D (Derstine, 1982) y HEXNOD (Gheorghiu, 1989;Bereznev, 2016).…”