Results 41 to 50 of about 1,135 (216)
Nuclear Engineering and Technology, 2016 A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic ...
Seok-Kyu Chang +5 more
doaj +1 more source
Energies, 2022 In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors.
Juan Carlos Almachi +2 more
doaj +1 more source
Performance analysis of cooperative NOMA systems with adaptive mode selection and subchannel allocation [PDF]
, 2019 In this paper, we study the mode selection and subchannel allocation for the downlink of a multi-user multi-subchannel cooperative non-orthogonal multiple access (C-NOMA) system.
Teh, Kah Chan +4 more
core +1 more source
Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
Nuclear Engineering and Technology, 2020 In nuclear engineering, the occurrence of critical heat flux (CHF) is complicated for rod bundle, and it is much more difficult to predict the CHF when it is in natural circulation under motion condition.
Siyang Huang +7 more
doaj +1 more source
FluidsComputational fluid dynamics (CFD) is an instrumental tool used in tackling the challenges of flow behavior and safety within nuclear reactor cores. Traditional CFD methods like finite volume, finite element, and finite difference have driven significant
Abutiatey Eugene, Pil-Seung Chung
doaj +1 more source
Subchannel Analysis of VVER-440 Using Subchanflow Code [PDF]
, 2020 Tato práce se zabývá modelováním konkrétních přechodových jevů pomocí subkanálové analýzy technologie VVER. První kapitola je věnována současnému stavu subkanálové analýzy.
Jan Syblík
core
Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor
Nuclear Engineering and Technology, 2019 The wire-wrapped fuel bundle is an assembly design in a sodium-cooled fast reactor. A wire spacer is used to maintain a constant gap between rods and to enhance the mixing of coolants.
Min Seop Song +2 more
doaj +1 more source
Adaptation of SUBCAL subchannel code for square-lattice rod bundles using PSBT benchmark
Acta Polytechnica CTU ProceedingsSubchannel analysis is a commonly used approach for simulating heat transfer and coolant flow in nuclear reactor cores. This paper presents the adaptation of the SUBCAL computational code, originally developed for reactors with a triangular lattice, to ...
Lucie Titzová +2 more
doaj +1 more source
Nanophotonics, Volume 15, Issue 14, 27 July 2026.This study demonstrates, for the first time, a 3D volumetric cylindrical vector beam (CVB) multicasting architecture that employs multichannel array modes with an operational dimension of 3 × 3 × 5 as information carriers. This approach offers substantial potential for high‐capacity information dissemination in mode‐multiplexed communication networks ...
Zhiqiang Xie +8 more
wiley +1 more source
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
, 2011 The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
core +1 more source