Results 41 to 50 of about 362 (143)
He jishu, 2021 BackgroundThe liquid-fueled molten salt reactor (MSR) is one of the Generation IV advanced reactor concepts, which has unique advantages in aspects of safety, economy and nonproliferation.
LI Rui, CHENG Maosong, DAI Zhimin
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.Sodium‐cooled fast reactor (SFR) is one of the fourth‐generation nuclear reactor types, which has inherent safety features such as low corrosion and no severe interaction between molten fuel and sodium. However, the severe accident of core melting in SFR needs to be considered.
Yingying Huo +3 more
wiley +1 more source
SCDAP/RELAP5 lower core plate model [PDF]
, 1999 The SCDAP/RELAP5 computer code is a best-estimate analysis tool for performing nuclear reactor severe accident simulations. This report describes the justification, theory, implementation, and testing of a new modeling capability which will refine the analysis of the movement of molten material from the core region to the vessel lower head.
Coryell, E. W., Griffin, F. P.
openaire +4 more sources
Numerical Study on Laminar-Turbulent Transition Flow in Rectangular Channels of a Nuclear Reactor
Frontiers 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
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International 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
International 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
Reactivity feedback effect on loss of flow accident in PWR
Nuclear 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
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Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model [PDF]
Journal 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
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Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor
Science 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
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Bayesian Uncertainty Quantification of Reflooding Model With PSO–Kriging and PCA Approach
Science 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