Journal ArticleDOI
LWR fuel rod behavior during severe accidents
S. Hagen,P. Hofmann +1 more
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TLDR
In this paper, the reaction kinetics of Zircaloy cladding with solid UO 2 fuel has been investigated with UO2 crucibles containing molten Ziraloy.About:
This article is published in Nuclear Engineering and Design.The article was published on 1987-08-01. It has received 14 citations till now. The article focuses on the topics: Zirconium alloy & Cladding (fiber optics).read more
Citations
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A review on the clad failure studies
TL;DR: The literature on clad failure has been broadly categorized under the headings LOCA and RIA as discussed by the authors, where the failure mechanisms like creep, corrosion and pellet-cloth interaction have been discussed in details.
Journal ArticleDOI
Interaction of Failed Fuel Rods Under Air Ingress Conditions
Zoltán Hózer,P. Windberg,Imre Nagy,László Maróti,L. Matus,M. Horváth,Anna Pintér Csordás,Márton Balaskó,Aladár Czitrovszky,Peter Jani +9 more
TL;DR: In this paper, two experiments were carried out with electrically heated nine-rod pressurized water reactor-type bundles in the CODEX (COre Degradation EXperiment) facility to provide experimental data on the behavior of real fuel bundles under air oxidation conditions.
Journal ArticleDOI
Behavior of vver fuel rods tested under severe accident conditions in the codex facility
Zoltán Hózer,László Maróti,P. Windberg,L. Matus,Imre Nagy,Gyorgy Gyenes,M. Horváth,A. Pintér,Márton Balaskó,Aladár Czitrovszky,Peter Jani,Attila Nagy,Oleg Prokopiev,B. Toth +13 more
TL;DR: In this paper, the early phase of severe accidents in WER reactors was simulated in the CODEX (COre Degradation Experiment) facility with electrically heated fuel rod bundles, which made possible the observation of specific phenomena, such as the protective role of oxide scale during quenching of high-temperature bundles, the composition of gases produced during the oxidation of boron-carbide control rods, and the interlink between the aerosol release and the oxidation process.
Journal ArticleDOI
Dissolution of solid UO2 by molten Zircaloy
M.S. Veshchunov,P. Hofmann +1 more
TL;DR: In this paper, a theoretical model is proposed which describes the material behavior during different stages of the chemical interaction process before and after liquid phase saturation in the first stage dissolution of UO2 and quick saturation of the Zircaloy melt by U and O atoms.
Journal ArticleDOI
Neutron multiplication in random media: Reactivity and kinetics parameters
TL;DR: In this article, the authors examined the behavior of the reactivity and of the kinetics parameters (the effective delayed neutron fraction and the effective neutron generation time) for three-dimensional UOX and MOX assembly configurations where a portion of the fuel pins has been randomly fragmented by using various mixing statistics.
References
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Journal ArticleDOI
UO2/zircaloy-4 chemical interactions from 1000 to 1700°C under isothermal and transient temperature conditions
P. Hofmann,D. Kerwin-Peck +1 more
TL;DR: In this article, chemical interactions between UO2 fuel and Zircaloy-4 cladding under isothermal and transient temperature conditions up to the melting point of Zry (Zry) are described.
Journal ArticleDOI
The UO2-Zircaloy chemical interaction
TL;DR: In this article, the authors analyzed existing experimental data on the interaction of uranium dioxide and Zircaloy with a model that accounts for the formation and growth of three corrosion layers between the oxide and the metal.
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Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C
TL;DR: In this article, the chemical interaction between solid and liquid Zircaloy-4 and solid UO2 was examined in the temperature region 1000 to 2000°C in argon.
Journal ArticleDOI
Explanation of the UO2/Zircaloy-4 Reaction layer sequence in terms of the total interfacial energy of the system
TL;DR: In this article, the UO2/Zircaloy-4 (Zry-4) interaction is explained in terms of the total interfacial energy and work of adhesion of the system.
Journal ArticleDOI
A model to describe the interaction between UO2 and zircaloy in the temperature range 1000–1700°C
Alicia Denis,Eduardo A. Garcia +1 more
TL;DR: In this article, the internal oxidation due to the reduction of the UO 2 pellets by the Zircaloy cladding material is analyzed, and a model is developed which solves only the oxygen diffusion problem in the five phases which are formed due to UO2 /Ziraloy interaction, without taking into account zirconium and uranium diffusion.