Results 21 to 30 of about 662,342 (249)

Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate

open access: yesNuclear Engineering and Technology, 2022
This paper presents a numerical investigation of two-phase natural circulation flows established when external reactor vessel cooling is applied to a severe accident of the APR1400 reactor for the in-vessel retention of the core melt.
Min Seop Song   +3 more
doaj   +1 more source

Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

open access: yesNuclear Engineering and Technology, 2022
The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART.
Sang Ho Kim   +6 more
doaj   +1 more source

Investigation of the probability of existence of defects with a size exceeding the allowed value

open access: yesStructural Mechanics of Engineering Constructions and Buildings, 2020
Relevance. Non-destructive testing of metal determines the actual state of the metal, the presence of discontinuities and their sizes, and also allows to determine what mechanisms of metal degradation were subjected to. One of the main characteristics of
Dmitry A. Kuzmin   +2 more
doaj   +1 more source

An experimental and computational study of the vortex shape in a partially baffled agitated vessel [PDF]

open access: yes, 2007
The vortex shape in a non-standard partially baffled agitated vessel in the form of a glass-lined, under-baffled stirred vessel has been investigated using both experimental and numerical approaches for an air/water system for different rotation speeds ...
Fletcher, David F.   +4 more
core   +1 more source

Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique

open access: yesNuclear Engineering and Technology, 2017
In-vessel retention by passive external reactor vessel cooling under severe accident conditions is a viable approach for retention of radioactive core melt within the reactor vessel.
Faruk A. Sohag   +6 more
doaj   +1 more source

Structured ZoneFlowTM-Bayonet Steam Reforming Reactor for Reduced Firing and Steam Export: Pressure Drop and Heat Transfer Modelling and Evaluation of the Reactor Performance

open access: yes, 2022
The ZoneFlow™ reactor is an annular structured reactor that offers lower pressure drop and significantly better heat transfer than standard pellets used in Steam Methane Reforming. The annular ZoneFlow™ reactor is particularly suited for use in a bayonet
Minette, Florent   +3 more
core   +1 more source

Effect of Tank Diameter on Solid Suspension in Industrial Reactor Vessels [PDF]

open access: yesJournal of Applied Fluid Mechanics
Present research study analyses the suitability of baffled reactor vessels with large diameter agitated using the Rushton Turbine (RT) impeller maintained at standard clearance condition for the solid-liquid suspension process.
D. K. Iyer, A. K. Patel
doaj   +1 more source

PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS

open access: yesJurnal Pendidikan Fisika Indonesia, 2014
Kelengkapan sistem keselamatan pasif dan inheren pada reaktor lanjut merupakan prasyarat utama. Makalah ini mengeksplorasi hasil desain konseptual sistem pembuang sisa panas pada pusat listrik tenaga nuklir berjenis Very High-Temperature Reactor.
A. G. Abdullah   +2 more
doaj   +1 more source

Leakage rate index allocation of reactor safety vessel for floating nuclear power plants

open access: yesZhongguo Jianchuan Yanjiu, 2022
ObjectiveThe purpose of this paper is to clarify the overall and local leakage rates of marine reactor safety vessel, establish the acceptance criteria of sealing test for reactor safety vessel and analyze the concentration of airborne radioactive ...
Gang JI   +4 more
doaj   +1 more source

Non-hardening embrittlement mechanism of pressure vessel steel Ni-Cr-Mo-V welds during thermal aging

open access: yesAdvances in Mechanical Engineering, 2020
The mechanical performance of reactor pressure vessel materials is an important factor in the safety and economics of the operation of a nuclear power plant.
Guojun Wei   +4 more
doaj   +1 more source

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