Results 51 to 60 of about 5,521 (168)

Efficient Numerical Modeling and Parametric Analysis of Solid Oxide Electrolysis Cells and Stacks for Nuclear Hydrogen Production

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
This study presents a numerical modeling approach for analyzing the electrochemical and thermal–hydraulic characteristics of solid oxide electrolysis (SOE) cells and stacks for hydrogen production. A semilumped parameter‐based simulation code was developed and validated using experimental data and literature references.
Jiwon Ahn   +3 more
wiley   +1 more source

Development of M5 Cladding Material Correlations in the TRANSURANUS Code: Revision 1 [PDF]

open access: yes, 2016
The technical report is based on an earlier research on material properties of the M5 structural material. Complementing this research with new M5 data found in open literature, a set of correlations has been developed for the implementation to the ...
HOLMSTROM BJORN   +3 more
core   +1 more source

Numerical Study on Laminar-Turbulent Transition Flow in Rectangular Channels of a Nuclear Reactor

open access: yesFrontiers in Energy Research, 2020
Laminar-turbulent transition flow can be observed in thermal engineering applications, but the flow resistance and heat transfer characteristics are not fully understood.
Zhenying Wang   +6 more
doaj   +1 more source

Parametric Analysis and Optimization of a Dual‐Fuel‐Fired Boiler for Power Generation Using the Taguchi Design Approach

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
Increased energy supply reliability, environmental sustainability, more competitive businesses, and improved standard of living are all made possible by more efficient energy conversion processes. In view of this, the present study aims at analysis and optimization of the operational parameters of a dual‐fuel‐fired boiler using Taguchi design method to
Sunday O. Oyedepo   +5 more
wiley   +1 more source

Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test

open access: yesScience and Technology of Nuclear Installations, 2017
The Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor for current ...
Noppawan Rattanadecho   +4 more
doaj   +1 more source

Reactivity feedback effect on loss of flow accident in PWR

open access: yesNuclear Engineering and Technology, 2018
In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents.
Basma Foad   +2 more
doaj   +1 more source

Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model [PDF]

open access: yesJournal of Applied and Computational Mechanics, 2017
Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the
Reza Akbari   +2 more
doaj   +1 more source

Bayesian Uncertainty Quantification of Reflooding Model With PSO–Kriging and PCA Approach

open access: yesScience and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
To improve the process of best estimate plus uncertainty (BEPU) for nuclear safety assessment and calibration of thermal–hydraulic models for error reduction, inverse uncertainty quantification (IUQ) is proposed in recent years to quantify the uncertainty of model parameters in reactor program.
Ziyue Zhang   +4 more
wiley   +1 more source

Thermo-hydraulic analysis of the windowless target system [PDF]

open access: yes, 2008
The target system, whose function is to supply an external neutron source to a subcritical core in order to sustain the neutron chain reaction, is the most critical part of an ADS being subject to severe thermo-mechanical loading and material damage due
Bianchi, Fosco   +2 more
core   +1 more source

Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor

open access: yesScience and Technology of Nuclear Installations, 2014
Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale.
Zhang Fan   +4 more
doaj   +1 more source

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