Results 141 to 150 of about 80,518 (195)

Thermal Conductivity of UO₂ with Defects via DFT+U Calculation and Boltzmann Transport Equation. [PDF]

Materials (Basel)
Qin J, Zhao M, Pan R, Tang A, Wu L.
europepmc   +1 more source

High Ionic Conduction in Rb- and Cs-Mixed Cation Amide for Energy Storage. [PDF]

Small
Le TT, Sellschopp K, Murgia F, Garden AL, Bordignon S, Embs JP, Chierotti MR, Schökel A, Karimi F, Jerabek P, Klassen T, Pistidda C.   +11 more
europepmc   +1 more source

Matrix-Embedding Effects on Nanodiamond Phonons. [PDF]

Nano Lett
Stamper C, Cortie DL, Bake A, Lewis RA, Yu D.   +4 more
europepmc   +1 more source

Fluctuation-driven topological Hall effect in room-temperature itinerant helimagnet Fe₃Ga₄. [PDF]

Nat Commun
Baral PR, Ukleev V, Živković I, Lee Y, Orlandi F, Manuel P, Skourski Y, Keller L, Stunault A, Rodríguez-Velamazán JA, Cubitt R, Magrez A, White JS, Mazin II, Zaharko O.   +14 more
europepmc   +1 more source

Viscosity as a Smoking Gun for Complex Formation in Solution: Fe²⁺ and Mg²⁺ Chlorides as Examples. [PDF]

J Phys Chem B
Goswami A, Blazquez S, Fernández-Sedano Vázquez L, Noya EG, Jónsson H, Troncoso J, Vega C.   +6 more
europepmc   +1 more source

High average-flux laser-driven neutron source. [PDF]

Nat Commun
Vallières S, Fillion-Gourdeau F, Fourmaux S, Poupart-Raîche B, Dietrich N, Beier NF, Lelièvre R, Catrix E, Maltais J, Hussein AE, Antici P, Légaré F, MacLean S.   +12 more
europepmc   +1 more source

Exploring Cyclodextrin-Based Nanosponges as Drug Delivery Systems: Evaluation of Spectroscopic Methods for Examining Structure and Dynamics of Nanosponges. [PDF]

Int J Mol Sci
Pyrak B, Rogacka-Pyrak K, Gubica T.
europepmc   +1 more source

Some of the next articles are maybe not open access.

Related searches:

Transport equation with delayed neutrons

Transport Theory and Statistical Physics, 1990
Abstract In nuclear fission reactor, the decay constant of delayed neutron will often determine the time behavior of the neutron population in a subcritical system or supercritical system or in a critical system in which a neutron source or cross section change with time.
openaire   +1 more source

Numerical solution of the neutron transport equation

Journal of Nuclear Energy, 1969
Abstract An outline of a procedure for directly solving the singular integral form of the one-speed neutron transport equation is given. The procedure is illustrated by considering the Milne problem and a one-region critical problem. Examples of numerical results obtained for these two problems are presented.
R.L. Bowden, A.G. Bullard
openaire   +1 more source

Eigenvalues of the neutron transport equation

Proceedings of the Physical Society, 1965
Results are given of the eigenvalues obtained for the neutron pulsed-source and diffusion-length problems using the gas kernel. Three methods of solution are reported: the diffusion approximation, the spherical harmonic (P3) approximation and the B0 approximation.
openaire   +1 more source