Results 21 to 30 of about 662,342 (249)
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
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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
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
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An experimental and computational study of the vortex shape in a partially baffled agitated vessel [PDF]
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
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
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]
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
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PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS
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
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
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

