Results 11 to 20 of about 4,161 (262)

Analysis of Methods and Technologies for Composition Assessing of Corium Formed as a Result of the Fukushima Daiichi NPP Accident

open access: yesГлобальная ядерная безопасность, 2022
This paper analyzes the methods and technologies for assessing the method of formation, composition, characteristics and features of corium, which is a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of an ...
S. N. Ryzhov   +6 more
doaj   +1 more source

VENOUS DRAINAGE OF THE CORIUM AND OTHER STRUCTURES OF THE FORE FOOT OF ONE-HUMPED CAMEL (Camelus dromedarius) [PDF]

open access: yesAssiut Veterinary Medical Journal, 1987
The study was undertaken to provide some informations aboutthe plexuses of the corium and the relations of the veins to other stuctures in connection with functions and surgical interference of the fore foot in the one-humped camel.
F.A. OSMAN   +2 more
doaj   +1 more source

Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2022
In this study, we investigated the characteristics of natural convection heat transfer of single-layer and two-layer corium pool in the elliptical lower head by the numerical method.
Y.P. Zhang   +6 more
doaj   +1 more source

Numerical simulation on heat transfer of VVER core cather

open access: yesHe jishu, 2023
BackgroundThe core corium may melt through the reactor pressure vessel wall then lead to the failure of the second barrier during a serious accident. Core catcher can collect and cool the corium and prevent the development of severe accident.PurposeThis ...
ZHU Guangyu   +4 more
doaj   +1 more source

Cationic local composition fluctuations in rapidly cooled nuclear fuel melts

open access: yesNuclear Materials and Energy, 2022
During a severe accident in a nuclear reactor, as it occurred in Fukushima Daiichi BWRs in 2011, the so-called “corium” resulting from the thermal fusion of nuclear fuel and interaction with the zircaloy cladding at high temperature (T > 2800 K) can be ...
Mohamed Jizzini   +4 more
doaj   +1 more source

High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

open access: yesFrontiers in Energy Research, 2022
During a severe accident in a nuclear reactor, the molten core—or corium—may be relocated into the reactor vessel’s lower plenum in case of core support plate failure.
Jules Delacroix   +2 more
doaj   +1 more source

Skora, corium, ledder

open access: yesHansische Geschichtsblätter, 2021
Skora, corium, ledder. Innovation und Professionalisierung im Lederhandwerk des südlichen Ostseeraums.
Joern-Martin Becker   +2 more
openaire   +2 more sources

NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT

open access: yesNuclear Engineering and Technology, 2013
The flow and heat transfer characteristics of the ex-vessel core melt (corium) were investigated using a commercial CFD code along with the experimental data on the spreading of corium available in the literature (VULCANO VE-U7 test).
IN-SOO YE   +5 more
doaj   +1 more source

Serdexmethylphenidate/dexmethylphenidate effects on sleep in children with attention-deficit/hyperactivity disorder

open access: yesFrontiers in Psychiatry, 2023
IntroductionSleep-related problems are common in children with attention-deficit/hyperactivity disorder (ADHD). Sleep disorders are also side effects of all stimulant ADHD medications.
Greg W. Mattingly   +5 more
doaj   +1 more source

Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition

open access: yesNuclear Engineering and Technology, 2016
A visualization test of the fuel–coolant interaction in the Test for Real cOrium Interaction with water (TROI) test facility was carried out. To experimentally simulate the In-Vessel corium Retention (IVR)- External Reactor Vessel Cooling (ERVC ...
Young Su Na   +3 more
doaj   +1 more source

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