J
Juri Stuckert
Researcher at Karlsruhe Institute of Technology
Publications - 108
Citations - 1159
Juri Stuckert is an academic researcher from Karlsruhe Institute of Technology. The author has contributed to research in topics: Zirconium alloy & Hydrogen. The author has an hindex of 19, co-authored 105 publications receiving 1032 citations.
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Synopsis and outcome of the QUENCH experimental program
TL;DR: The QUENCH program at the Karlsruhe Institute of Technology (KIT) as mentioned in this paper has performed 15 integral bundle experiments with 21-31 electrically heated fuel rod simulators of 2.5-m length.
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Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation
TL;DR: The influence of the oxide layer morphology on the hydrogen uptake during steam oxidation of (Zr,Sn) and Zr-Nb nuclear fuel rod cladding alloys was investigated in isothermal separate-effect tests and large-scale fuel rod bundle simulation experiments as discussed by the authors.
Journal ArticleDOI
Core Loss during a Severe Accident (COLOSS).
B. Adroguer,F. Bertrand,P. Chatelard,N. Cocuaud,J. P. Van Dorsselaere,L. Bellenfant,D. Knocke,D. Bottomley,V. Vrtilkova,L. Belovsky,K. Mueller,Wolfgang Hering,C. Homann,W. Krauss,A. Miassoedov,G. Schanz,Martin Steinbrück,Juri Stuckert,Zoltán Hózer,Giacomino Bandini,J. Birchley,T.v. Berlepsch,I. Kleinhietpass,Michael Buck,J.A.F. Benitez,E. Virtanen,S. Marguet,G. Azarian,A. Caillaux,H. Plank,A.V. Boldyrev,M.S. Veshchunov,V.L. Kobzar,Yu.A. Zvonarev,A. V. Goryachev +34 more
TL;DR: In this paper, a parallel effort is devoted to model developments for severe accident (SA) computer codes, and these codes are finally used for plant calculations to assess SA code capabilities and to apply results produced in this project to evaluate their consequences on key SA sequences occurring in different plants such as PWR-1300, BWR, VVER-1000, EPR and in the TMI-2 accident.
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High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
Martin Steinbrück,J. Birchley,A.V. Boldyrev,A. V. Goryachev,Mirco Grosse,Tim Haste,Zoltán Hózer,A. E. Kisselev,V. I. Nalivaev,V. P. Semishkin,L. Sepold,Juri Stuckert,N. Vér,M.S. Veshchunov +13 more
TL;DR: In this paper, the status of knowledge of high-temperature oxidation of the two zirconium alloys Zircaloy-4 and E110 with special emphasis on results obtained during the SARNET period is discussed.
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Experiments on air ingress during severe accidents in LWRS
TL;DR: In this article, various kinds of experiments on the oxidation of Zircaloy-4 cladding material in different scales and under different conditions at temperatures 800 -1300 -C and up to 2000 -C were presented.