Results 51 to 60 of about 12,472 (163)

Optimization of Performance, Price, and Background of Long Neutron Guides for European Spallation Source

open access: yesQuantum Beam Science, 2019
We describe a systematic approach for the design of long, ballistic cold, and thermal neutron guides for the European Spallation Source (ESS). The guides investigated in this work are 170 m long and are required to have a narrowing point with room for a ...
Sonja Holm-Dahlin   +4 more
doaj   +1 more source

Development of a reliable estimation procedure of radioactivity inventory in a BWR plant due to neutron irradiation for decommissioning

open access: yesEPJ Web of Conferences, 2017
Reliable information of radioactivity inventory resulted from the radiological characterization is important in order to plan decommissioning planning and is also crucial in order to promote decommissioning in effectiveness and in safe.
Tanaka Ken-ichi, Ueno Jun
doaj   +1 more source

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

open access: yesEPJ Web of Conferences, 2017
Nuclear decommissioning takes place in several stages due to the radioactivity in the reactor structure materials. A good estimation of the neutron activation products distributed in the reactor structure materials impacts obviously on the ...
Lee Yi-Kang
doaj   +1 more source

Sobolev Regularity in Neutron Transport Theory [PDF]

open access: yesISRN Mathematical Analysis, 2012
The main purpose of this paper is to extend the W1,p regularity results in neutron transport theory, with respect to the Lebesgue measure due to Mokhtar-Kharroubi, (1991), and to abstract measures covering, in particular, the continuous models or multigroup models.
openaire   +2 more sources

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

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 numerical validation between the neutron transport and diffusion theories for a spatial kinetics problem

open access: yesBrazilian Journal of Radiation Sciences
In this paper, a comparative analysis of numerical results of the neutron transport and diffusion theories for steady-state and transient multigroup problems is presented.
Rodrigo Zanette   +2 more
doaj   +1 more source

Jacobian-Free Newton Krylov Methods for Steady and Transient Neutron Transport Models

open access: yesYuanzineng kexue jishu
There is an urgent need to reduce the computational costs and improve the convergence rate for the three-dimensional (3D) high-fidelity pin-by-pin full core simulation.
ZHANG Yangyi, ZHANG Tiancheng, ZHOU Xiafeng
doaj   +1 more source

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