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      Pressure surge in Wendelstein 7-X experimental stellarator facility Translated title: Druckstösse im Stellaratorexperiment Wendelstein 7-X

      1 , 2 , 3
      Carl Hanser Verlag

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          Fusion is the energy production technology, which could potentially solve problems with growing energy demand of population in the future. Wendelstein 7-X (W7-X) is an experimental stellarator facility currently being built in Greifswald, Germany, which shall demonstrate that in the future energy could be produced in such type of fusion reactors. Lithuanian energy institute (LEI) in the frames of European Fusion Development Agreement (EFDA) program is cooperating with Max Planck Institute for Plasma Physics (IPP, Germany) by performing safety analysis of fusion device W7-X. In this paper the consequences of potential water hammer effects were analysed only for the case, when the plasma vessel is operating in the “baking” mode. “Baking” is the mode of facility operation during which the plasma vessel structures are heated up to 150°C in order to release absorbed gases from the surfaces and to pump them out of the plasma vessel before plasma operation. For the analysis the thermal-hydraulic model of target (torus) modules cooling / heating systems in W7-X facility was developed using RELAP5/Mod3.3 code. The performed analyses showed that the pressure pulsations in pipelines of cooling / heating systems are possible only in case of very fast closure of automatic valves in torus modules inlets and check valves in torus modules outlets. The maximum dynamic loading to cooling / heating systems pipelines due to such valves activations is in the range 0.12–0.28 MPa. Such dynamic load is insignificant and integrity of pipelines remains not violated. The pressure surge in pipeline connecting torus module in case of erroneous closure of automatic valve is eliminated due to operation of check valve on pipeline in torus module outlet.


          Wendelstein 7-X (W7-X) ist ein Stellaratorexperiment, das derzeit in Greifswald, Deutschland gebaut wird. Dieses soll zeigen, dass in Stellaratoren Energie erzeugt werden kann. Im Rahmen des European Fusion Development Agreement (EFDA) Programms arbeitet das Litauische Energy Institute (LEI) mit dem Max-Planck-Institut für Plasmaphysik (IPP, Deutschland) auf dem Gebiet der Sicherheitsanalysen zusammen.

          In diesem Beitrag werden die Folgen potentieller Druckstöße während der Betriebsart “baken“ untersucht. Beim “baken“ werden die Plasmakesselstrukturen auf Temperaturen bis zu 150°C erhitzt, um absorbierte Gase von den Oberflächen zu lösen und aus dem Plasmagefäß zu pumpen.

          Für die Analyse wurde ein thermohydraulisches Modell der Torusmodule zur Kühlung und Aufheizung der W7-X Anlage für das Programm RELAP5/Mod3.3 entwickelt. Die durchgeführten Analysen zeigen, dass Druckschläge in den Rohrleitungen der Kühl-/Heizsysteme nur möglich sind, wenn automatische Ventile in den Eingangsöffnungen und Rückschlagsventile in den Ausgangsöffnungen sehr schnell geschlossen werden. Dabei werden Druckstöße im Bereich von 0,12 bis 0,28 MPa erreicht. Diese dynamischen Belastungen sind gering und beeinträchtigen die Integrität der Rohrleitungen nicht.

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          Benchmarking analysis of water hammer effects using RELAP5 code and development of RBMK-1500 reactor main circulation circuit model

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            Analysis of the processes in the target cooling system of the W7-X fusion experiment

            Nuclear fusion has the potential to cover a major part of mankind's energy needs under the conditions of ever-increasing population and energy consumption. Wendelstein 7-X (W7-X) is a fusion experiment currently being built in Greifswald, which shall demonstrate the capability of the stellarator concept on the way to a fusion power plant. This paper presents analyses of processes in the target cooling system with the codes RELAP5 and ASTEC. The loss-of-coolant accident (LOCA) during the “baking” operation mode of W7-X (i.e. under the most critical conditions because of the high temperature and pressure applied) is analysed. The response of the W7-X “baking” and main cooling circuits and the amount of coolant discharged into the plasma vessel are investigated.

              Author and article information

              Carl Hanser Verlag
              : 77
              : 2
              : 134-140
              1 E-mail: algis@ 123456mail.lei.lt
              2 E-mail: uspuras@ 123456mail.lei.lt
              3 PhD student (corresponding author). E-mail: tadas@ 123456mail.lei.lt Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos g. 3, Kaunas LT–44403, Lithuania
              © 2012, Carl Hanser Verlag, München
              : 21 November 2011
              Page count
              References: 10, Pages: 7
              Technical Contributions/Fachbeiträge

              Materials technology,Materials for energy,Nuclear physics
              Materials technology, Materials for energy, Nuclear physics


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