Analytic solution of two-group static neutron diffusion equation using different transverse leakage approximations in 2D cartesian geometry [PDF]
Nodal is a method for solving the neutron diffusion equation. It is categorized to analytic, semi-analytic and expansion nodal methods. In this research work, a software is developed in order to solve two group neutron diffusion equations in two ...
Mohammad Hosseini +2 more
doaj
Adaptive solution of the domain decomposition+L2-jumps method applied to the neutron diffusion equation on structured meshes [PDF]
At the core scale, neutron deterministic calculations are usually based on the neutron diffusion equation. Classically, this equation can be recast in a mixed variational form, and then discretized by using the Raviart-Thomas-Nédélec Finite Element.
Gervais Mario +3 more
doaj +1 more source
Atomistic Mechanisms Triggered by Joule Heating Effects in Metallic Cu‐Bi Nanowires for Spintronics
Bi doped metallic Cu nanowires are promising for spintronics thanks to the stabilization of a giant spin Hall effect. However, heat resulting from current injection forces Bi to leave solution, forcing segregation into monoatomic decorations which evolve into coherent crystalline aggregates.
Alejandra Guedeja‐Marrón +6 more
wiley +1 more source
Groups of equivalency in the problems of neutron diffusion within heterogeneous medium
An application of group equivalence transformations for generating solutions of neutron diffusion equation in heterogeneous medium from solutions for homogeneous medium is studied.
I. M. Tsyfra
doaj +1 more source
Understanding Operando Water Management in Hydroxide‐Exchange‐Membrane Fuel Cells
Effective water management is vital for high‐performance hydroxide‐exchange‐membrane fuel cells. Using a custom water‐flux station, this study quantifies how membrane thickness, microporous layers, and operating conditions dictate internal water transport.
Catherine M. Weiss +4 more
wiley +1 more source
NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK
The paper describes a new numerical code for multigroup transient analyses with thermal feedback. The code is developed at Institute of Nuclear and Physical Engineering.
Filip Osuský +5 more
doaj +1 more source
New 3D Diffusion Code Based on The Nodal Polynomial Expansion
Nodal Expansion Method (NEM) is widely employed in the neutronic design of nuclear reactors core. The main reason is its higher computational performance and efficiency when compared with the conventional fine mesh difference method or finite element ...
Jadna Mara Santos Mendes +2 more
doaj +1 more source
Advances in Halide Perovskites for Photon Radiation Detectors
This work highlights recent progress in perovskite‐based photon radiation detectors, covering organic–inorganic hybrid, inorganic, lead‐free double, and vacancy‐ordered halide perovskites. Their detection performance is compared, material‐specific advantages and challenges are examined, and provides insight into current limitations and future ...
Liangling Wang +3 more
wiley +1 more source
The 10B‐enriched monocarbonyl analog of curcumin (BMAC) 10B‐9 enables site‐specific Boron Neutron Capture Therapy (BNCT) on amyloid‐β (Aβ) fibrils. Neutron irradiation induces histidine oxidation and fibril destabilization, as revealed by 1H‐NMR and FESEM analyses.
Sebastiano Micocci +13 more
wiley +1 more source
We describe in this work the application of the modified power method for solve the multigroup neutron diffusion eigenvalue problem in slab geometry considering two-dimensions for nuclear reactor global calculations.
Rodrigo Zanette +2 more
doaj +1 more source

