12 skills found
imronuke / KOMODOOpen Nuclear Reactor Simulator
imronuke / ADPRESAn Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
Zonni / FEMFFUSIONRepository of FEMFFUSION: a finite element code for nuclear reactor modelling. FEMFFUSION is an open source C++ neutronic code to solve the multigroup neutron diffusion equation with the finite element method. FEM + DIFFUSION = FEMFFUSION.
NEMO-Group / NemoFoamMultiphysics (neutron diffusion + thermal-hydraulics) model for OpenFOAM
YangYuSCU / DE PINNwith comprehensive numerical study on solving neutron diffusion eigenvalue problems) We present a data-enabled physics-informed neural network (DEPINN) with comprehensive numerical study for solving industrial scale neutron diffusion eigenvalue problems (NDEPs). In order to achieve an engineering acceptable accuracy for complex engineering problems, a very small amount of prior data from physical experiments are suggested to be used, to improve the accuracy and efficiency of training. We design an adaptive optimization procedure with Adam and LBFGS to accelerate the convergence in the training stage. We discuss the effect of different physical parameters, sampling techniques, loss function allocation and the generalization performance of the proposed DEPINN model for solving complex problem. The feasibility of proposed DEPINN model is tested on three typical benchmark problems, from simple geometry to complex geometry, and from mono-energetic equation to two-group equations. Numerous numerical results show that DEPINN can efficiently solve NDEPs with an appropriate optimization procedure. The proposed DEPINN can be generalized for other input parameter settings once its structure been trained. This work confirms the possibility of DEPINN for practical engineering applications in nuclear reactor physics.
ImperialCollegeLondon / ReCoDE Diffusion CodeRepository for the ReCoDE project which aims to solve the Neutron Diffusion Equation
friedmud / GardensnakeClass Project Simple finite-volume based neutron diffusion solver using MOOSE
NielsBongers / Neutron Transport Monte CarloEnergy-dependent neutron transport Monte Carlo implemented in Rust.
bearsan / FDM SCM For Neutron DiffusionTest code for 2D transient neutron diffusion equation based on the finite difference method (FDM) and stiffness confinement method (SCM).
wbinventor / 18.335 Final ProjectA Jacobian Free Newton Krylov solver with geometric multigrid preconditioning for the 2D LRA neutron diffusion benchmark problem.
nfherrin / OpenNodalAn open source nodal solver for nuclear reactors.
pdarnowski / REACTOR PHYSICS SIMPLE CODESMATLAB codes to study the basic of Nuclear Reactor Physics. Includ: diffusion 1D/0D codes, single and multigroup, point burnup calculations, point neutron kinetics and dynamics and point Xenon & Samarium transients.
