Results 31 to 40 of about 24,771 (208)
With ever-advancing computer technology, the Monte Carlo (MC) neutron transport calculation is expanding its application area to nuclear reactor transient analysis.
Nadeem Shaukat, Min Ryu, Hyung Jin Shim
doaj +1 more source
Neutrino treatment in multidimensional astrophysical simulations : a new spectral scheme [PDF]
Neutrinos play a central role in modern physics and astrophysics. Their extremely weak interaction rate with baryons and other leptons makes their detection on the Earth difficult and challenging.
Perego, Albino
core +1 more source
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares +2 more
doaj +1 more source
Skin effect in neutron transport theory [PDF]
We identify a neutron-flux "skin effect" in the context of neutron transport theory. The skin effect, which emerges as a boundary layer at material interfaces, plays a critical role in a correct description of transport phenomena. A correct accounting of the boundary-layer structure helps bypass computational difficulties reported in the literature ...
E. L. Gaggioli +2 more
openaire +4 more sources
Topics in Core-Collapse Supernova Theory: The Formation of Black Holes and the Transport of Neutrinos [PDF]
Core-Collapse Supernovae are one of the most complex astrophysical systems in the universe. They deeply entwine aspects of physics and astrophysics that are rarely side by side in nature.
O'Connor, Evan Patrick
core +1 more source
The shielding calculation of neutron streaming problems with ducts is characterized by the strong anisotropy of angular flux, which poses a challenge for the analysis of nuclear installations.
Xinyu Wang +3 more
doaj +1 more source
ANALYSIS AND COMPARISON OF APOLLO3® AND TRIPOLI-4® NEUTRON NOISE SOLVERS [PDF]
Neutron noise analysis addresses the description of small time-dependent flux fluctuations in reactor cores, induced by small global or local perturbations of the macroscopic cross sections due to density fluctuations of the coolant, to vibrations of ...
Rouchon Amélie +2 more
doaj +1 more source
Simulating neutron transport in long beamlines at a spallation neutron source using Geant4
The transport of neutrons in long beamlines at spallation neutron sources presents a unique challenge for Monte-Carlo transport calculations. This is due to the need to accurately model the deep-penetration of high-energy neutrons through meters of thick
Dijulio, Douglas D. +9 more
core +1 more source
A series of higher-order Ruddlesden-Popper phase materials – La3PrNi3O10-d, La2Pr2Ni3O10-d and LaPr3Ni3O10-d – were synthesised and investigated by neutron powder diffraction to understand the oxygen defect structure and propose possible pathways for ...
Ieuan, Seymour +2 more
core +1 more source
lp-CMFD acceleration schemes in multi-energy group 2D Monte Carlo transport
The linear prolongation flux update scheme is extended to both regular CMFD acceleration, as well as partial CMFD acceleration in 2D multi energy group Monte Carlo k-eigenvalue neutron transport problems.
Y. R. Than, S. Xiao
doaj +1 more source

