Results 11 to 20 of about 788 (153)

Adjusting the nuclear reactor's neutron transport and diffusion theory for an alternative description and modelling of postage or supplies delivery processes

open access: yes, 2021
There seems to exist significant similarities between a reactor system and a supply chain from collection to delivery. In the reactor case, neutrons are continuously produced and absorbed in nuclear fuel. In a supply system case, items are continuously collected and continuously delivered to destinations.
openaire   +2 more sources

Perturbation Theory-Based Whole-Core Eigenvalue Sensitivity and Uncertainty (SU) Analysis via a 2D/1D Transport Code

open access: yesScience and Technology of Nuclear Installations, 2020
For nuclear reactor physics, uncertainties in the multigroup cross sections inevitably exist, and these uncertainties are considered as the most significant uncertainty source. Based on the home-developed 3D high-fidelity neutron transport code HNET, the
Ji Ma, Chen Hao, Lixun Liu, Yuekai Zhou
doaj   +1 more source

Pin-by-pin Calculation of Reactor Core-Based on Quasi-diffusion in Rectangular Grid

open access: yesYuanzineng kexue jishu, 2023
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety analysis. The second generation of core calculation theory and methods based on advanced component homogenization theory and modern coarse grid block ...
YAN Jiangtao;LIU Kun;ZHUANG Kun;WANG Senshan;ZHANG Kaihui;ZHANG Xinxin
doaj  

Tuning the Mechanical Properties of Crosslinked Copolymers via Sequence and Solvent‐Selective Swelling for Vat Photopolymerization

open access: yesAngewandte Chemie, EarlyView.
Polymer sequence and solvent selectivity independently modulate pendant‐vinyl accessibility during photocuring, trapping different topologies in CLIP and controlling mechanical properties. ABSTRACT Block copolymers (BCPs) offer distinct advantages for vat photopolymerization by enabling mechanically programmable network structures through microphase ...
Chia‐Min Hsieh   +12 more
wiley   +2 more sources

Neutron transport analysis for nuclear reactor design [PDF]

open access: yes, 2023
Replacing regular mesh-dependent ray tracing modules in a collision/transfer probability (CTP) code with a ray tracing module based upon combinatorial geometry of a modified geometrical module (GMC) provides a general geometry transfer theory code in two

core  

A comparative study of 10 different methods on numerical solving of point reactor neutron kinetics equations

open access: yes, 2017
Point reactor neutron kinetics equations describe the time dependent neutron density variation in a nuclear reactor core. These equations are widely applied to nuclear system numerical simulation and nuclear power plant operational control.
Zhang, H.   +3 more
core   +1 more source

Percolation properties of the neutron population in nuclear reactors

open access: yes, 2022
Reactor physics aims at studying the neutron population in a reactor core under the influence of feedback mechanisms, such as the Doppler temperature effect.
Delcambre, Thomas   +2 more
core   +1 more source

The Influence of Neighbouring Clouds on the Clear Sky Reflectance Studied with the 3-D Transport Code RADUGA

open access: yes, 2005
Operational remote sensing of terrestrial atmosphere is heavily based on the 1-D radiative transfer equation. However, cloudy scenes are influenced by 3-D effects (e.g., illumination from cloud sides, etc.).
Nikolaeva, O.V.   +5 more
core   +1 more source

The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport Simulation [PDF]

open access: yes, 2021
Department of Nuclear EngineeringReactor core analysis has been increasingly advanced, but neutron transport/diffusion two-step analysis codes developed several decades ago are still widely used in the actual design.
Choe, Jiwon
core  

Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module

open access: yesEPJ Nuclear Sciences & Technologies, 2016
In nuclear safety research, the quality of the results of simulation codes is widely determined by the reactor design and safe operation, and the description of neutron transport in the reactor core is a feature of particular importance.
Labarile Antonella   +4 more
doaj   +1 more source

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