Results 1 to 10 of about 308 (180)

Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

open access: yesEnergies, 2022
Subchannel codes have been widely used for thermal-hydraulics analyses in nuclear reactors. This paper details the development of a novel subchannel code within the Idaho National Laboratory’s (INL) Multi-physics Object Oriented Simulation Environment ...
Vasileios Kyriakopoulos   +2 more
doaj   +3 more sources

Evaluation of ATLHAMC12 subchannel code for total loss of flow scenario

open access: yesActa Polytechnica CTU Proceedings, 2023
The ALTHAMC12 subchannel code is a new subchannel code developed by the ALVEL company. The code is intended for DNBR safety analyses of the Czech nuclear power plants.
Tomáš Křeček, Štěpán Foral
doaj   +2 more sources

Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code

open access: yesJournal of Nuclear Science and Technology, 1995
Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged ...
INOUE, Akira   +5 more
exaly   +2 more sources

Uncertainty Quantitative Analysis of Subchannel Code Calculation of PSBT Void Distribution Benchmark

open access: yesShanghai Jiaotong Daxue xuebao, 2022
In order to evaluate the accuracy and reliability of the subchannel code, it is necessary to quantitatively give the uncertainty of the calculation results.
ZHANG Juntao, LIU Xiaojing, ZHANG Tengfei, CHAI Xiang
doaj   +1 more source

Demonstration of Pronghorn’s Subchannel Code Modeling of Liquid-Metal Reactors and Validation in Normal Operation Conditions and Blockage Scenarios

open access: yesEnergies, 2023
Pronghorn-SC is a subchannel code within the Multiphysics Object-Oriented Simulation Environment (MOOSE). Initially designed to simulate flows in water-cooled, square lattice, subchannel assemblies, Pronghorn-SC has been expanded to simulate liquid-metal-
Vasileios Kyriakopoulos   +2 more
doaj   +1 more source

Thermal hydraulic analysis of a PWR loaded with annular fuel rods

open access: yesBrazilian Journal of Radiation Sciences, 2021
In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of ...
Wallen Ferreira De Souza   +3 more
doaj   +1 more source

Interpolative multiresolution coding of advance television with compatible subchannels [PDF]

open access: yesIEEE Transactions on Circuits and Systems for Video Technology, 1991
A multiresolution representation for video signals is introduced. A three-dimensional spatiotemporal pyramid algorithms for high-quality compression of advanced television sequences is presented. The scheme utilizes a finite memory structure and is robust to channel errors, provides compatible subchannels, and can handle different scan formats, making ...
Kamil Metin Uz   +2 more
openaire   +1 more source

SUBSALS: a subchannel thermal-hydraulic code for IRT type fuel analysis

open access: yesActa Polytechnica CTU Proceedings, 2022
The LVR-15 research reactor is operated with a tube type fuel IRT-4M. Due to fuel’s unique concentric square annular shape with, coolant flow is subject to significant pressure driven crossflow.
Tomáš Adámek
doaj   +1 more source

Proposal of point-wise power reconstruction for IRT-4M fuel assemblies in coupled Monte-Carlo calculations

open access: yesActa Polytechnica CTU Proceedings, 2022
Current efforts to develop high-fidelity multi-physics tools for research reactors with IRT-4M fuel leads to the involvement of Monte-Carlo transport and subchannel thermo-hydraulic codes in the process of safety assessment.
Pavel Jíška, Jan Frýbort
doaj   +1 more source

Core thermal-hydraulics analysis during dipped-type direct heat exchanger operation in natural circulation conditions

open access: yesMechanical Engineering Journal, 2022
A direct reactor auxiliary cooling system (DRACS) under natural circulation (NC) conditions with a dipped-type direct heat exchanger (D-DHX) in the upper plenum of a reactor vessel (RV) has been investigated for enhancing the safety of sodium-cooled fast
Erina HAMASE   +5 more
doaj   +1 more source

Home - About - Disclaimer - Privacy