Results 171 to 180 of about 30,351 (207)
Multiplex nodal modularity: A novel network metric for the regional analysis of amnestic mild cognitive impairment during a working memory binding task. [PDF]
PLoS OneCampbell-Cousins A +4 more
europepmc +1 more source
Quantum mechanical dataset of 836k neutral closed-shell molecules with up to 5 heavy atoms from C, N, O, F, Si, P, S, Cl, Br. [PDF]
Sci DataKhan D +4 more
europepmc +1 more source
Some of the next articles are maybe not open access.
Related searches:
Related searches:
The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
Kerntechnik, 2013Abstract The reactor dynamics code DYN3D is a three-dimensional best-estimate tool for simulating steady states and transients of light-water reactors and innovative reactor designs. An overview of the DYN3D features is provided. This paper further focuses on the recently developed trigonal-geometry diffusion model DYN3D-TRIDIF including
Duerigen, S. +3 more
openaire +4 more sources
Annals of Nuclear Energy, 2020
Abstract SN nodal method has been successfully applied to fast reactor core neutronics analysis. The computational efficiency can be enhanced efficiently by the popular coarse-mesh finite difference (CMFD) method. However, the CMFD method suffers from the problem of instability, especially for optically thick problems.
Zhitao Xu +3 more
openaire +3 more sources
Abstract SN nodal method has been successfully applied to fast reactor core neutronics analysis. The computational efficiency can be enhanced efficiently by the popular coarse-mesh finite difference (CMFD) method. However, the CMFD method suffers from the problem of instability, especially for optically thick problems.
Zhitao Xu +3 more
openaire +3 more sources
NEMSQR: A 3-D multi group diffusion theory code based on nodal expansion method for square geometry
Annals of Nuclear Energy, 2014Abstract A three dimensional, multigroup, neutron diffusion theory based computer code NEMSQR ( N odal E xpansion M ethod for SQ uare geometry) is developed for square geometry in order to perform reactor core calculation. The code is based on Nodal Expansion Method (NEM).
Tej Singh +2 more
openaire +3 more sources
Annals of Nuclear Energy, 2021
Abstract The rod ejection accident (REA) is the most severe reactivity-initiated accident of the pressurized water reactors (PWRs). The three-dimensional (3-D) neutron kinetics method is widely applied to the REA analysis, where the fixed neutron source is usually ignored at the hot zero power (HZP) condition. This paper describes a new capability of
YuGwon Jo, Ho Cheol Shin
openaire +1 more source
Abstract The rod ejection accident (REA) is the most severe reactivity-initiated accident of the pressurized water reactors (PWRs). The three-dimensional (3-D) neutron kinetics method is widely applied to the REA analysis, where the fixed neutron source is usually ignored at the hot zero power (HZP) condition. This paper describes a new capability of
YuGwon Jo, Ho Cheol Shin
openaire +1 more source
Kerntechnik, 2015
Abstract In this paper, we developed a new approach of analytic function expansion nodal (AFEN) method to solve the multi-group and multi-dimensional neutron diffusion equation in reactor cores with hexagonal fuel assembly. This method represents a multidimensional intra nodal flux distribution in terms of analytic basis functions at any
M. H. Jalili Bahabadi +2 more
openaire +1 more source
Abstract In this paper, we developed a new approach of analytic function expansion nodal (AFEN) method to solve the multi-group and multi-dimensional neutron diffusion equation in reactor cores with hexagonal fuel assembly. This method represents a multidimensional intra nodal flux distribution in terms of analytic basis functions at any
M. H. Jalili Bahabadi +2 more
openaire +1 more source
Kerntechnik, 2017
Abstract Continuous-energy Monte Carlo reactor physics code Serpent 2 was used to model the critical steady state conditions measured in V-1000 zero-power critical facility at Kurchatov Institute (KI), Moscow in 1990–1992. The Serpent 2 results were compared to measurements and Serpent 2 was used to generate group constants for reactor ...
Sahlberg, Ville
openaire +4 more sources
Abstract Continuous-energy Monte Carlo reactor physics code Serpent 2 was used to model the critical steady state conditions measured in V-1000 zero-power critical facility at Kurchatov Institute (KI), Moscow in 1990–1992. The Serpent 2 results were compared to measurements and Serpent 2 was used to generate group constants for reactor ...
Sahlberg, Ville
openaire +4 more sources
Kerntechnik, 2019
Abstract The C-PORCA/HELIOS models have been used at NPP Paks as basic core neutron physics calculation tools for many years. C-PORCA is a node-wise diffusion model for the purpose of 3D core analysis. HELIOS is a well-known neutron transport code. Its utilisation at Paks NPP has a dual use.
I. Pós +4 more
openaire +1 more source
Abstract The C-PORCA/HELIOS models have been used at NPP Paks as basic core neutron physics calculation tools for many years. C-PORCA is a node-wise diffusion model for the purpose of 3D core analysis. HELIOS is a well-known neutron transport code. Its utilisation at Paks NPP has a dual use.
I. Pós +4 more
openaire +1 more source
Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-I: Theory
International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022Thomas Folk +4 more
openaire +1 more source