Results 21 to 30 of about 10,122 (257)

Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies [PDF]

open access: yesHe jishu
BackgroundSubchannel analysis of fuel assemblies is critical for the development of lead-bismuth reactors.PurposeThis study aims to modify and optimize the COBRA subchannel program to make it suitable for lead-bismuth reactors and validate its ...
WANG Yan   +4 more
doaj   +2 more sources

Numerical Simulation of Water-Based Alumina Nanofluid in Subchannel Geometry [PDF]

open access: yesScience and Technology of Nuclear Installations, 2012
Turbulent forced convection flow of Al2O3/water nanofluid in a single-bare subchannel of a typical pressurized water reactor is numerically analyzed.
Mohammad Nazififard   +3 more
doaj   +2 more sources

Analysis of Subchannel and Rod Bundle PSBT Experiments with CATHARE 3 [PDF]

open access: yesScience and Technology of Nuclear Installations, 2012
This paper presents the assessment of CATHARE 3 against PWR subchannel and rod bundle tests of the PSBT benchmark. Noticeable measurements were the following: void fraction in single subchannel and rod bundle, multiple liquid temperatures at subchannel ...
M. Valette
doaj   +2 more sources

Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA [PDF]

open access: yesScience and Technology of Nuclear Installations, 2012
In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5
Dae-Hyun Hwang   +3 more
doaj   +2 more sources

Mechanism Model of Critical Heat Flux in Bundle Based on High-precision Subchannel Code [PDF]

open access: yesYuanzineng kexue jishu, 2023
Critical heat flux (CHF) is a crucial safety limit for PWR core design. Accurately predicting CHF in the core rod bundle channel can enhance the economy and safety of the reactor. Currently, the prediction of rod bundle CHF in engineering is mainly based
GUO Junliang;JIANG Li;GAO Kui;KONG Huanjun;GUI Miao;SHAN Jianqiang
doaj   +2 more sources

DEVELOPMENT OF 3D PIN-BY-PIN CORE SOLVER TORTIN AND COUPLING WITH THERMAL-HYDRAULICS [PDF]

open access: yesEPJ Web of Conferences, 2021
Currently, safety analyses mostly rely on codes which solve both the neutronics and the thermal-hydraulics with assembly-wise nodes resolution as multiphysics heterogeneous transport solvers are still too time and memory expensive.
Mala P.   +3 more
doaj   +1 more source

Deep Learning Based Radio Resource Management in NOMA Networks: User Association, Subchannel and Power Allocation [PDF]

open access: yesIEEE Transactions on Network Science and Engineering, 2020
With the rapid development of future wireless communication, the combination of NOMA technology and millimeter-wave(mmWave) technology has become a research hotspot.
Haijun Zhang   +3 more
semanticscholar   +1 more source

Joint Subchannel and Power Allocation for NOMA Enhanced D2D Communications [PDF]

open access: yesIEEE Transactions on Communications, 2017
In this paper, a novel non-orthogonal multiple access (NOMA) enhanced device-to-device (D2D) communication scheme is considered. Our objective is to maximize the system sum rate by optimizing subchannel and power allocation.
Jingjing Zhao   +4 more
semanticscholar   +2 more sources

Development and application of multi-scale thermal fluid coupling program for molten salt cooled fast reactor based on RELAP5 and sub-channel program

open access: yesHe jishu, 2022
BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential.
SONG Shiyang   +3 more
doaj   +1 more source

Flow Characteristics within an Interior Subchannel of a 61-pin Wire-Wrapped Hexagonal Rod Bundle with a Porous Blockage

open access: yesThe Physics of Fluids, 2023
Potential accumulation of undesirable debris in a subchannel of a Liquid Metal Fast Reactor (LMFR) hexagonal fuel bundle presents accident conditions, which are crucial to investigate.
Craig Menezes   +4 more
semanticscholar   +1 more source

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