Results 91 to 100 of about 24,771 (208)

Sparse Macro-track Transport Acceleration Method for 3-D Pebble-bed Geometry

open access: yesYuanzineng kexue jishu
The method of characteristics has very strong geometric adaptability and can be used to solve the 3-D whole core problem of high temperature gas-cooled pebble-bed reactor.
GUO Jian1, GUO Jiong2, LI Fu2, YAN Rui1, ZOU Yang1
doaj   +1 more source

Galactic cosmic ray modulation near the heliospheric current sheet

open access: yes, 2014
Galactic cosmic rays (GCRs) are modulated by the heliospheric magnetic field (HMF) both over decadal time scales (due to long-term, global HMF variations), and over time scales of a few hours (associated with solar wind structures such as coronal mass ...
Owens, M. J.   +7 more
core   +1 more source

Hybrid solvers for reactor modelling: matrix-based and matrix-free approaches on voxel-dominated meshes

open access: yesFrontiers in Nuclear Engineering
Simulating neutronics and thermal hydraulics within nuclear reactor cores is computationally intensive, not only because of the complexity of the governing equations but also because of the intricate geometries involved.
Liang Yang   +4 more
doaj   +1 more source

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

open access: yesYuanzineng 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

The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method

open access: yesMATEC Web of Conferences, 2018
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear fuel cell using Collision Probability (CP) method has been done.
Shafii Mohammad Ali   +3 more
doaj   +1 more source

A multi-region collision probability method for determining neutron spectra and reaction rates

open access: yes, 2012
textThe collision probability approach to neutron transport can be used to obtain the energy-dependent neutron spectrum in nuclear reactor systems as well as other quantities of interest.
Dembia, Christopher Lee
core  

Determination of Pure Neutron Radiolysis Yields for use in Chemical Modeling of Supercritical Water

open access: yes, 2007
This work has determined pure neutron radical yields at elevated temperature and pressure up to supercritical conditions using a reactor core radiation.
Edwards, Eric
core  

Benchmarking Geant4 for spallation neutron source calculations

open access: yes, 2016
Geant4 is becoming increasingly used for radiation transport simulations of spallation neutron sources and related components. Historically, the code has seen little usage in this field and it is of general interest to investigate the suitability of ...
Dijulio, Douglas D.   +9 more
core   +1 more source

Solar neutron transport in the earth's atmosphere

open access: yes, 1967
Solar neutron transport in Earth atmosphere from neutron spectral ...
Boughner, R. T., Alsmiller, R. G., Jr.
core  

Adaptive discontinuous Galerkin methods for the neutron transport equation [PDF]

open access: yes, 2014
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  

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