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      The development and assessment of TRACE model for Lungmen ABWR Translated title: Entwicklung und Anwendung eines TRACE Datensatzes für den Reaktor Lungmen (ABWR) in Taiwan

      1 , 2 , 3
      Carl Hanser Verlag

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          For the nuclear power plant Lungmen (two blocks of Advanced Boiling Water Reactor (ABWR)) in Taiwan a plant model for the thermal hydraulic program TRACE (TRAC/RELAP Advanced Computational Engine) was developed. This model is and will be used for the simulation of normal and anomalous plant behaviour as well as for the simulation of incident scenarios. The presentation of this model is done in three steps: The first step is the development of a TRACE model of Lungmen nuclear power plant (NPP) which includes the vessel, the main steam lines and important control systems (such as the feedwater control system, recirculation flow control system, etc.). Key parameters were identified to refine the model further in the frame of a steady state analysis. The second step is the performance of TRACE transient analyses, such as MSIV closure direct scram (MSIVCD, MSIV = Main Steamline Isolation Valve) and loss of feedwater flow (LOFW). The above transient data of Final Safety Analysis Report (FSAR) are used to verify the Lungmen NPP TRACE model. The trends of their analysis results are roughly similar. It indicates that TRACE model is satisfying for the purpose of Lungmen NPP safety analyses. The third step is the prediction analysis of Lungmen NPP startup tests by using the TRACE model. The prediction analysis results of TRACE comply with the startup tests procedure criteria.


          Für das in Bau befindliche Kernkraftwerk Lungmen (2 Blöcke des Typs Advanced Boiling Water Reactor (ABWR)) in Taiwan wurde für die Simulation des normalen sowie anomalen Betriebes sowie von Störfällen ein Anlagenmodell für das Thermohydraulikprogrammsystem TRACE (TRAC/RELAP Advanced computational Engine) erstellt, das in dem vorliegenden Beitrag im Detail beschrieben wird. Hierbei wird speziell auf die Nodalisierung des Reaktordruckbehälters sowie des Kühlsystems eingegangen. Mit dem Anlagenmodell konnten die Systemparameter im stationären Betrieb, die in der Regel den Anfangsbedingungen für die Simulation einer Transiente bzw. eines Kühlmittelverluststörfalls entsprechen, gut reproduziert werden. Anschließend werden die Ergebnisse der Simulation verschiedener Störfälle im Detail und an den diesbezüglichen Ausführungen des sog. Final Safety Analysis Report (FSAR) gespiegelt. Hierbei zeigt sich eine gute qualitative und weitgehend auch quantitative Übereinstimmung. Abschließend werden erste Vorausrechnungen ausgewählter Inbetriebnahmeversuche der Anlage vorgestellt.

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          Most cited references2

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          TRACE modeling and its verification using Maanshan PWR start-up tests

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            Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5


              Author and article information

              Carl Hanser Verlag
              : 76
              : 3
              : 205-215
              1 E-mail: htlin@ 123456iner.gov.tw
              2 E-mail: jrwang@ 123456iner.gov.tw Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C. No. 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (R.O.C.)
              3 Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013, Taiwan (R.O.C.). E-mail: ckshih@ 123456ess.nthu.edu.tw
              © 2011, Carl Hanser Verlag, München
              : 08 February 2010
              Page count
              References: 13, Pages: 11
              Technical Contributions/Fachbeiträge

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


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