Results 121 to 130 of about 6,219 (301)

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, Luca Weckelmann, Baolin Wu, Chih‐Long Tsai, Luc Raijmakers, Rüdiger‐A. Eichel, Anna Windmüller   +6 more
wiley   +1 more source

The discrete ordinates method for the neutron transport equation in an infinite cylindrical domain

, 1992
We prove a regularity result for a Fredholm integral equation with weakly singular kernel, arising in connection with the neutron transport equation in an infinite cylindrical domain. The theorem states that the solution has almost two derivatives in L1,
Asadzadeh, Mohammad,, Kumlin, Peter,, Larsson, Stig,   +2 more
core   +1 more source

Dual Activation of H2 and CO2 by a Pincer‐Type Ni–Zn Heterobimetallic Complex

Angewandte Chemie, EarlyView.
A bimetallic Ni−Zn complex performs sequential activations of H2 (1 equiv) and CO2 (2 equiv). This bimetallic cooperativity is attributed to the weak Lewis acidic nature of Zn(II), which promotes fluxional ligand binding. Namely, an X‐type ligand at Ni, where X is hydride or formate, toggles between two different binding modes: bridging Zn(μ‐X)Ni and ...
Krishnendu Dey, Matthias Borowski, Gregor Schnakenburg, Connie C. Lu   +3 more
wiley   +2 more sources

U1 and P1 approximations to neutron transport equation for diffusion length calculation

, 2013
U-1 and P-1 approximations are used for the calculation of asymptotic relaxation length in one-dimensional neutron transport equation. The approximation methods are applied to anisotropic neutron transport equation with backward and forward scattering ...
Bulbul, A., Ozturk, H.
core  

A Quantitative Lithium Inventory Framework for Anode‐Free Lithium Metal Batteries

Advanced Energy Materials, EarlyView.
A component‐resolved lithium inventory framework quantitatively tracks Li redistribution across the cell in anode‐free NMC622||Cu pouch cells throughout cycling. Three sequential degradation stages are identified: formation‐driven cathode Li depletion, midlife inactive Li0 accumulation, and late‐stage runaway SEI thickening. The cathode, as the sole Li
Wurigumula Bao, Alex Liu, Thomas S. Marchese, Yuanlong Bill Zheng, Weikang Li, Dhevathi Rajan Rajagopalan Kannan, Vallabha Rao Rikka, Vinay Premnath, Judith Jeevarajan, Ying Shirley Meng   +9 more
wiley   +1 more source

Deterministic Calculation Method for Continuous-energy Neutron Transport Equation in No-resonance Energy-range

Yuanzineng kexue jishu
In analyzing the power density distribution within the core of a nuclear reactor, it is necessary to employ numerical methods to solve the neutron transport equation and obtain the neutron flux density distribution.
LIU Haopo, LI Yunzhao, WU Hongchun, CAO Liangzhi
doaj   +1 more source

Hydrodynamics coupled circulating-fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors

Nuclear Engineering and Technology
Effects of relative motion between moving fuel and neutrons are usually not considered in the analysis of Circulating Fuel Reactors (CFRs). In this study, we formulate neutron transport equation for CFRs in a hydrodynamic representation in terms of ...
Ayhan Yılmazer, Gökhan Pediz
doaj   +1 more source

Mechanisms of Alkali Ionic Transport in Amorphous Oxyhalides Solid State Conductors

Advanced Energy Materials, EarlyView.
Large‐scale machine learning‐based molecular dynamics simulations are used to investigate isovalent amorphous oxyhalides, revealing a remarkable chemically independent ionic conductivity. A rigorous analysis of alkali residence times across different metal–anion environments identifies divalent anions as key diffusion bottlenecks.
Luca Binci, KyuJung Jun, Bowen Deng, Gerbrand Ceder   +3 more
wiley   +1 more source

Adaptive discontinuous Galerkin methods for the neutron transport equation

In this thesis we study the neutron transport (Boltzmann transport equation) which is used to model the movement of neutrons inside a nuclear reactor. More specifically we consider the mono-energetic, time independent neutron transport equation.
Bennison, Tom
core  

Deterministic numerical methods for unstructured mesh neutron transport calculation /

, 2020
Includes index.Intro -- Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation -- Copyright -- Contents -- Contributors -- Foreword -- Preface -- Chapter 1: Neutron transport equation -- 1.1. Introduction -- 1.2.
Wu, Hongchun., Cao, Liangzhi.
core