Results 11 to 20 of about 12,613 (263)
Investigation of the probability of existence of defects with a size exceeding the allowed value
Structural 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
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Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique
Nuclear 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
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Effect of Tank Diameter on Solid Suspension in Industrial Reactor Vessels [PDF]
Journal of Applied Fluid MechanicsPresent 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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Reactor vessel sectioning demonstration [PDF]
, 1981 A technical demonstration was successfully completed of simulated reactor vessel sectioning using the combined techniques of air arc gouging and flame cutting. A 4-ft x 3-ft x 9-in. thick sample was fabricated of A36 carbon steel to simulate a reactor vessel wall. A 1/4-in. layer of stainless steel (SS) was tungsten inert gas (TIG)-welded to the carbon
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PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS
Jurnal 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
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Leakage rate index allocation of reactor safety vessel for floating nuclear power plants
Zhongguo 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
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Non-hardening embrittlement mechanism of pressure vessel steel Ni-Cr-Mo-V welds during thermal aging
Advances 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
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, 1961 Two types of bellows configurations were proposed for the HNPF Reactor Vessel. It was established that the only logical manner of comparing the two designs is on an actual stress basis which implies equal life for each bellows. Results are presented giving the minimum number of convolutions required for each design. (auth)
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CFD analysis of coolant flow in the nuclear reactor VVER440 [PDF]
Applied and Computational Mechanics, 2007 The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the reactor pressure vessel (RPV) outlet and under the RPV head.
Katolický J. +3 more
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Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions
Science and Technology of Nuclear Installations, 2022 In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants.
Shilei Han +3 more
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