Results 1 to 10 of about 4,217 (206)
Evaluation of ATLHAMC12 subchannel code for total loss of flow scenario
Acta 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
Energies, 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 +1 more source
Uncertainty Quantitative Analysis of Subchannel Code Calculation of PSBT Void Distribution Benchmark
Shanghai 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
Energies, 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
Brazilian 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
SUBSALS: a subchannel thermal-hydraulic code for IRT type fuel analysis
Acta 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
Acta 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
Interpolative multiresolution coding of advance television with compatible subchannels [PDF]
IEEE 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
Mechanical 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
Nuclear Engineering and Technology, 2018 There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the computing
Seok Jong Yoon +4 more
doaj +1 more source