Results 81 to 90 of about 19,203 (311)
NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK
Acta Polytechnica CTU Proceedings, 2016 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
DIFF, a code to prepare neutron diffusion theory parameters from the results of the code WDSN.
, 1967 With a solution of the multigroup neutron transport equation available for a problem in one dimensional geometry, diffusion theory parameters are determined so as to reproduce in diffusion theory the essential characteristics of the transport solution ...
Manning, G, Spinks, N
core
Sulfide‐Based Electrolytes for All‐Solid‐State Sodium Batteries
Advanced Energy Materials, EarlyView.This review covers the structural features and synthesis strategies of sulfide‐based solid electrolytes, as well as critical challenges related to conductivity, interfacial and moisture stability, and scaling‐up for practical application in Sodium‐based All Solid‐State Batteries.
Han Yang +6 more
wiley +1 more source
Investigation of Neutron Diffusion Length in Wax Medium [PDF]
, 2011 The investigation of the damage tracks of Pu (Be) neutron source by using solid state nuclear track detector in the wax medium was performed. Using the neutron tracks and neutron diffusion equation, neutron diffusion length in wax medium was ...
San Yee
core
Advanced Energy Materials, EarlyView.Oxygen substitution in NaTaOxCl6‐2x drives structural evolution from isolated [TaCl6]– octahedra, through oxygen‐bridged [Ta2OCl10]2– dimers, toward extended trans‐[TaO2Cl4]3– chain‐like arrangements. At intermediate compositions, zero‐dimensional corner‐sharing motifs are proposed to create a flexible, disordered framework that peaks ionic ...
Justin Leifeld +17 more
wiley +1 more source
La diffusion des neutrons [PDF]
Revue de Physique Appliquée, 1976 On rappellera les bases physiques de la diffusion des neutrons en insistant sur les caractéristiques du phénomène qui la différencie de la diffusion des rayons X, en particulier l'existence d'une diffusion inélastique dont le spectre en énergie peut être déterminé.
openaire +1 more source
Accuracy of the diffusion theory component of removal-diffusion theory.
, 1976 The neutron fluxes in five neutron shields consisting of water, concrete, graphite, iron and an iron-water lattice respectively, have been calculated using P1 theory, diffusion theory with the usual transport correction for anisotropic scattering (DT ...
Donnelly, IJ
core
Advanced Energy Materials, EarlyView.Silicon anodes in sulfide SSBs face coupled electrochemo‐mechanical failure by interface instability. This review examined recent advances and proposed mitigation strategies via material‐, electrode/interface‐, and cell‐level‐ engineering. We further evaluate scalable synthesis of sulfide SEs.
Murugesan Karuppaiah +4 more
wiley +1 more source
Role of neutron transfer and deformation effect in capture process at sub-barrier energies
EPJ Web of Conferences, 2012 The roles of nuclear deformation and neutron transfer in sub-barrier capture process are studied within the quantum diffusion approach. The change of the deformations of colliding nuclei with neutron exchange can crucially influence the sub-barrier ...
Scheid W. +4 more
doaj +1 more source
Nuclear Engineering and Technology, 2019 A new moving-mesh Finite Volume Method (FVM) for the efficient solution of the two-dimensional neutron diffusion equation is introduced. Many other moving-mesh methods developed to solve the neutron diffusion problems use a relatively large number of ...
Mehran Vagheian +2 more
doaj +1 more source