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atw - International Journal for Nuclear Power | 10.2020

Description Ever since its first issue in 1956, the atw – International Journal for Nuclear Power has been a publisher of specialist articles, background reports, interviews and news about developments and trends from all important sectors of nuclear energy, nuclear technology and the energy industry. Internationally current and competent, the professional journal atw is a valuable source of information. www.nucmag.com

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Ever since its first issue in 1956, the atw – International Journal for Nuclear Power has been a publisher of specialist articles, background reports, interviews and news about developments and trends from all important sectors of nuclear energy, nuclear technology and the energy industry. Internationally current and competent, the professional journal atw is a valuable source of information.

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<strong>atw</strong> Vol. 65 (2020) | Issue 10 ı October<br />

where the heat transfer is recalculated<br />

during the interaction, to consider<br />

the effect of a variable decay heat,<br />

<strong>for</strong> example. This requires further<br />

investigation in order to identify as<br />

many influencing parameters as<br />

possible and to incor porate them<br />

into the correlation.<br />

References<br />

[AGE18] K. Agethen, M. Hoffmann, M.K. Koch: Analyse und<br />

Bewertung der COCOSYS-Modellbasis zu Ex-Vessel<br />

Phänomenen während MCCI. Technischer Fachbericht<br />

zum Forschungsvorhaben BMWi 1501512, AG Plant<br />

Simulation and Safety, Ruhr-Universität Bochum,<br />

2018, PSSTR3.<br />

[ALS86] H. Alsmeyer, C. Adelhelm, H.-G. Dillmann, J. Foit, M.<br />

Heinle, W. Ratajczak, H. Schneider, G. Schumacher,<br />

A. Skokan, S. Stiefel, W. Tromm; BETA experiments on<br />

melt-concrete interaction: the role of Zirconium and<br />

the potential sump water contact during melt-down<br />

accidents. Bd. 154. 61-68 No. 1. DOI: 10.1016/<br />

0029-5493(94)00898-9. – <strong>Nuclear</strong> Engineering und<br />

Design, 1986, S. 61–68.<br />

[ALS92] H. Alsmeyer: Proceedings of the Second OECD (NEA)<br />

CSNI Specialist Meeting on Molten Core Debris-<br />

Concrete Interactions, OECD <strong>Nuclear</strong> Energy Agency in<br />

collaboration with Kern<strong>for</strong>schungszentrum Karlsruhe,<br />

April 1992, NEA/CSNI/R(92)10.<br />

[ALS95] H. Alsmeyer, G. Cenerino, E. Cordfunke, D. Fioravanti,<br />

M. Fischer, J. Folt, L. Howe, M. Huntelaar, S. Locatelli,<br />

F. Parozzi, J. Szabo, B. Turland, M. Vidard, D. Wegener;<br />

Molten corium/concrete interaction and corium<br />

coolability - A state of the art report. (EUR16649),<br />

European Commision - <strong>Nuclear</strong> Science und<br />

Technology, 1995.<br />

[ALL07] H.-J. Allelein, S. Arndt, W. Klein-Heßling, K. Neu, N.<br />

Reinke, S. Schwarz, B. Schwinges, C. Spengler,<br />

G. Weber: Intensivierte Validierung der<br />

Rechenprogramme COCOSYS und ASTEC, Final Report,<br />

November 2007, GRS-A-3330.<br />

[CRA13] M. Cranga, C. Spengler, K. Atkhen, S. Bechta,<br />

P. Bottomley, P. Dejardin, A. Fargette, M. Fischer,<br />

J.J. Foit, R. Gencheva, P. Grudev, E. Guyez, J.F. Haquet,<br />

C. Journeau, G. Langrock, B. Michel, C. Mun, G. Ratel,<br />

T. Sevon, B. Spindler: State-of-the-Art-Report on MCCI<br />

in dry conditions: Analysis of experiments, modelling<br />

and reactor applications, IRSN, August 2013, PSN-<br />

RES/SAG/2013-00076.<br />

[FOI19] J.J. Foit, T. Cron, B. Fluhrer: Melt/Concrete Interface<br />

Temperature relevant to MCCI Process, Karlsruhe<br />

Institute of Technology (KIT), The 9 th European Review<br />

Meeting on Severe Accident Research (ERMSAR2019),<br />

March 2019<br />

[PEE83] M. Peehs, R. Höpfl, B. Gather, R. Blachnik: Die<br />

integrale Schmelzeenthalpie von Reaktorbeton<br />

als thermophysikalische Eingangsgröße von<br />

Unfallfolgemoedellen des hypothetischen<br />

Kernschmelzeunfalls, <strong>Journal</strong> of <strong>Nuclear</strong> Materials 118<br />

p. 206-213, 1983.<br />

[SPE12] C. Spengler, S. Arndt, J. Arndt, J. Bakalov, S. Band,<br />

J. Eckel, W. Klein-Hessling, H. Nowack, M. Pelzer,<br />

N. Reinke, J. Sievers, M. Sonnenkalb, G.Weber;<br />

Weiterentwicklung der Rechenprogramme COCOSYS<br />

and ASTEC – Abschlussbericht. (GRS – A – 3654),<br />

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS)<br />

mbH, 2012.<br />

[SPE18] C. Spengler et al., “Uncertainty and Sensitivity<br />

Analyses in Support of Model Development and<br />

Validation of the Containment Module COCOSYS<br />

of the AC2 Code - Application <strong>for</strong> Molten Corium/<br />

Conrete Interaction (MCCI),” in Proceedings of<br />

NUTHOS-12, Qingdao, China, 2018.<br />

Authors<br />

Maximilian Hoffmann<br />

maximilian.hoffmann@pss.rub.de<br />

Prof. Marco K. Koch<br />

Ruhr-Universität Bochum<br />

Plant Simulation and Safety Group<br />

Universitätsstraße 150<br />

44801 Bochum, Germany<br />

Imprint<br />

Imprint<br />

Official <strong>Journal</strong> of Kerntechnische Gesellschaft e. V. (KTG)<br />

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ISSN 1431-5254<br />

RESEARCH AND INNOVATION 513

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