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

