Relevant bibliographies by topics / University Library Zittau/Görlitz

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  1. Journal articles
  2. Dissertations / Theses
  3. Conference papers

Academic literature on the topic 'University Library Zittau/Görlitz'

Author: Grafiati
Published: 4 June 2021
Last updated: 10 February 2022

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Journal articles on the topic "University Library Zittau/Görlitz"

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Müller, Cornelia. "Sports, home and health as motives for German-Polish school cooperation." International Journal of Pedagogy, Innovation and New Technologies 4, no. 2 (December 28, 2017): 48–57. http://dx.doi.org/10.5604/01.3001.0011.5844.

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The following paper contains a report on an international school project – GESZKO ‒, that had been taking place in the border area of Saxony and Poland in the school years 2011/12, 2012/13 and 2013/14. The main theme of the activities at 13 schools were health, sport and home region. After the end of the project the team at the University of Applied Science in Zittau/Görlitz is evaluating the entire project and is going to publish a manual for German-Polish school partnerships.
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Höhne, T., E. Krepper, and U. Rohde. "Application of CFD Codes in Nuclear Reactor Safety Analysis." Science and Technology of Nuclear Installations 2010 (2010): 1–8. http://dx.doi.org/10.1155/2010/198758.

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Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety (NRS) analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail. Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR) have been performed at the FZD for almost a decade. The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX. In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated. Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.
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Dissertations / Theses on the topic "University Library Zittau/Görlitz"

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Elger, Maria, David Pidde, and Ralf Schwarzbach. "Getürmtes Wissen." Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2009. http://nbn-resolving.de/urn:nbn:de:bsz:14-ds-1244016978863-04546.

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Die Idee für das im Folgende beschriebene Kunstprojekt entstand im Sommer 2008 beim Besuch der Prager Stadtbibliothek, wo eine Buchskulptur des Künstlers Matej Kren steht. Die Vorstellung, dass dies auch in Zittau möglich ist, stieß bei der Direktorin der Hochschulbibliothek Frau Dr. R. Konschak auf großes Interesse. Mit Prof. Dr.-Ing. J. Tomlow war schnell der richtige Ansprechpartner im Fachbereich Bauwesen gefunden.
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Konschak, Rosemarie. "Die Flut 2010 in Ostsachsen." Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-63325.

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Der Dauerregen Anfang August in Ostsachsen ließ uns in Zittau unmutig zum grauen Himmel blicken. Am 7. August, einem Samstag, spitzte sich innerhalb kürzester Zeit alles dramatisch zu. Regenmengen von 160 l/m2 ließen die Neiße und ihren kleinen Nebenfluss Mandau bis zu ihren Dammkronen ansteigen. Die Hochschulbibliothek Zittau/Görlitz war im Jahre 2006 am Standort Zittau in einen Neubau nahe der Mandau eingezogen. Die Haupträume befinden sich im Erdgeschoss und in der ersten Etage, das Magazin wurde jedoch im Kellergeschoss untergebracht. Das Bibliotheksteam wies während der Bauphase nachdrücklich auf mögliche Hochwassergefahren für das Magazin hin. Die Bedenken wurden mit der Begründung abgewiesen, dass sie nur bei einem „Jahrhunderthochwasser“ berechtigt seien. Dieses „Jahrhundert“ war am 7. August 2010 um 18.30 Uhr abgelaufen.
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Bove, Jens, and Marc Rohrmüller. "Das Mühlenarchiv Günter Rapp." Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2006. http://nbn-resolving.de/urn:nbn:de:swb:14-1156334955071-48147.

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"Wissenschaftliche Berichte / Hochschule Zittau/Görlitz, University of Applied Sciences." Hochschule Zittau/Görlitz, University of Applied Sciences, 2020. https://slub.qucosa.de/id/qucosa%3A72176.

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Conference papers on the topic "University Library Zittau/Görlitz"

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Fiß, Daniel, Sebastian Schmidt, Sebastian Reinicke, and Alexander Kratzsch. "Fundamental R&D Work on Methods for State Monitoring of Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67245.

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The continuing search for a long-term storage for highly-active nuclear waste in Germany requires a prolonged intermediate storage period of spent fuel in dry storage casks at the power plant sites. Currently, it is not sufficiently clear if there might be a loss of integrity of the fuel rods within such long periods, e.g. due to rising pressure from gaseous products of nuclear decay. Regarding a final evaluation, extrapolative modelling of the radiochemical and thermomechanical material behavior is challenging and not suitable for predictions on the condition of storage container inventory after the intermediate storage period. Therefore, it is of public interest to find measurement principles or methods which can provide information about the condition of the storage container inventory. In line with a cooperative project (project partners: Technical University Dresden, Zittau/Görlitz University of Applied Sciences) different measurement principles and methods (radiation emission, muon transmission, thermography, acoustical spectrometry) for non-invasive condition monitoring of the storage container inventory in case of prolonged intermediate storage are going to be investigated and evaluated. The results shall help to determine suitable methods for the identification of both changes of the spent fuel and inner container structure over long periods without opening the container and would be a significant contribution for the long-term safety of intermediately stored highly radioactive waste. Furthermore, suitable methods would provide information about the transport and conditioning ability of the waste before transfer to the repository. This paper deals with the content of the subproject of Zittau/Görlitz University of Applied Sciences as well as with the approach for project realization. A further main part of this paper is the development of experimental infrastructure to support the investigations.
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Schneider, Günter. "ABOUT INTERCULTURAL EDUCATION IN CONJUNCTION WITH THE STUDIUM FUNDAMENTALE (STUDIUM GENERALE) AT THE UNIVERSITY OF APPLIED SCIENCES ZITTAU / GÖRLITZ." In ЯЗЫК. КУЛЬТУРА. ПЕРЕВОД = LANGUAGE. CULTURE. TRANSLATION. Science and Innovation Center Publishing House, 2019. http://dx.doi.org/10.12731/lct.2019.41.

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The article presents the interdisciplinary and general education courses in Studium fundamentale. In doing so, a way of the university for more interdisciplinary teaching offers for listeners of all faculties is described. It describes a way of integrating intercultural education into bachelor's programs (engineering, social sciences, natural sciences and economics). A number of sources provide further information on the state of general education at universities and colleges in Saxony.
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Brachem, Carsten, Jörg Konheiser, and Uwe Hampel. "The Gamma Radiation Emitted by a PWR Core Under Severe Accident Conditions." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30843.

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The gamma radiation emitted by a nuclear reactor core might contain information about the reactor state. This information may be used in a monitoring system for severe accidents. The Technische Universität Dresden and the Zittau/Görlitz University of Applied Sciences are currently carrying out feasibility studies for the development of such a system in a collaborative effort. As one part of such feasibility studies we performed Monte Carlo simulations on a simplified model of a generic pressurized water reactor. For a set of states which represent scenarios of a coolant level decrease and core melt, the gamma radiation distribution outside the reactor pressure vessel has been computed. The results are presented in this paper. They indicate that different coolant levels yield different gamma radiation distributions, and that an accumulation of corium inside the lower head is detectable from the outside.
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Kryk, Holger, Ulrich Harm, and Uwe Hampel. "Corrosion of Hot-Dip Galvanized Containment Installations: A Potential Cause for Thermal-Hydraulic Effects After LOCA in PWR?" In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60273.

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Generic investigations regarding the influence of corrosion processes of hot-dip galvanized PWR containment installations on strainer clogging as well as on the coolant chemistry and possible resulting in-core effects are carried out within joint research projects of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), TU Dresden (TUD) and Zittau-Görlitz University of Applied Sciences (HSZG). Lab-scale experiments at HZDR and TUD are focused on elucidation of physico-chemical corrosion and precipitation processes as well as resulting clogging effects. Results of generic experiments in a lab-scale corrosion test facility suggest that there is a multi-stage corrosion process. The first stage comprises dissolution of the zinc layer in the coolant forming zinc ions and in turn affecting the coolant chemistry. During the second stage, the base material (steel) corrodes forming insoluble corrosion particles, which can subsequently lead to accelerated clogging of fiber-laden strainers within a few hours. The main influences on corrosion were identified as impact of the coolant jet onto the corroding surface, water chemistry and zinc surface / coolant volume ratio. Furthermore, retrograde solubility of zinc corrosion products in boric acid containing coolants with increasing temperature was observed. Thus, formation and deposition of solid corrosion products cannot be ruled out if zinc containing coolant is heated up during its recirculation into hot downstream components (e.g. hot-spots in core). Corrosion experiments, which included formation of corrosion products at a heated cladding tube, proved that zinc, dissolved in the coolant at low sump temperatures, turns into solid deposits of zinc borates when contacting heated zircaloy surfaces. Due to alternating heating and cooling of the coolant during sump recirculation operation, a cycle of zinc corrosion and zinc borate precipitation may be initiated, which may eventually influence the thermal hydraulics in downstream components during the post-LOCA stage. The results obtained at lab-scale were confirmed by corresponding experiments in semi-technical test facilities of the project partner HSZG. Based on the experimental results, water chemical measures were tested to reduce corrosion and/or zinc borate precipitation effects.
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Renger, Stefan, Sören Alt, Wolfgang Kästner, and André Seeliger. "Investigations About Released Debris and Corrosion Products and Their Impact to Head Loss Build Up and Decay Heat Removal Under Water-Chemical PWR-LOCA Conditions." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60261.

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Investigations about the release, transportation and deposit of fibrous insulation material (FIM), corrosion products as well as resulting compounds and debris mixtures become more important to reactor safety research, when considering long-term behavior of emergency core cooling systems (ECCS) during loss of coolant accidents (LOCA). Debris released by a leakage jet leads to head loss buildups at the sump strainers, the debris filters and the spacers of fuel assemblies. However, these complex processes may influence the decay heat transfer out of the reactor core. A similar but newer scenario implies that the boric acid coolant in pressurized water reactors (PWR) can support corrosion processes at hot-dip galvanized installations, leading to a significant release of ionic zinc into the coolant during the sump recirculation phase. A long-term change of chemical properties of the coolant (e.g. pH, zinc ion concentration) has to be considered in safety analyses. Chemical analyses showed that the solubility of zinc in boric acid coolant is inversely proportional to the coolant temperature. Consequently, zinc ions can be dissolved at lower temperatures in the containment sump. Precipitations of zinc borate (ZBP) are possible at hot spots in the reactor core. The ZBP can be formed as a flocculent disperse phase in the coolant or as solidified layers at hot fuel rod surfaces. Layer spalling could lead to the release of further solid particles into coolant flow inside the reactor core. In several joint research projects between the Zittau/Görlitz University of Applied Sciences (HSZG) and the Helmholtz-Zentrum Dresden-Rossendorf (HZDR) investigations on the impact of these processes to the head loss buildup and the heat transfer from core were done at laboratory and semi-technical scaled test facilities. Generic experiments showed the formation of ZBP in heating rod configurations. The ZBP may remain in the core structures or can be transported on debris filter cakes in upstream and downstream components of ECCS and influence the head loss. After this, research addressed the systematical clarification of physico-chemical mechanisms and their influence on thermal-hydraulic-dynamic processes occurring as a consequence of flow induced corrosion effects during LOCA. This paper includes a description of the most important involved test facilities, applied measuring techniques, an overview of boundary conditions considered experimentally and selected results.
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