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      Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis Translated title: Eignung der TRACE-Modelle zur Berechnung der Gegenstrombegrenzung und der kritischen Strömung bei der Anwendung in LBLOCA-Berechnungen für das Kernkraftwerk Maanshan

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          Abstract

          This study aims to develop the Maanshan Pressurized Water Reactor (PWR) analysis model by using the TRACE (TRAC/RELAP Advanced Computational Engine) code. By analyzing the Large Break Loss of Coolant Accident (LBLOCA) sequence, the results are compared with the Maanshan Final Safety Analysis Report (FSAR) data. The critical flow and Counter Current Flow Limitation (CCFL) play an important role in the overall performance of TRACE LBLOCA prediction. Therefore, the sensitivity study on the discharge coefficients of critical flow model and CCFL modeling among different regions are also discussed. The current conclusions show that modeling CCFL in downcomer has more significant impact on the peak cladding temperature than modeling CCFL in hot-legs does. No CCFL phenomena occurred in the pressurizer surge line. The best value for the multipliers of critical flow model would be 0.5 and the TRACE could consistently predict the break flow rate in the LBLOCA analysis as shown in FSAR.

          Kurzfassung

          Für das Kernkraftwerk Maanshan vom Typ DWR wurde und werden Sicherheitsuntersuchungen mit dem Programm TRACE (TRAC/RELAP Advanced Computational Engine) durchgeführt. In diesem Beitrag werden Ergebnisse von Berechnungen grosser Brüche (LBLOCA) unter besonderer Berücksichtigung der Gegenstrombegrenzung (CCFL) und der kritischen Strömung vorgestellt. Die Ergebnisse dieser aktuellen Berechnungen werden mit den Daten aus dem Maanshan Sicherheitsbericht (FSAR) verglichen. Dabei zeigt sich, dass die Berücksichtigung von CCFL im Downcomer einen stärkeren Einfluss auf die maximale Hüllrohrtemperatur hat als die Berücksichtigung des CCFL in den heißen Strängen. In der Surge Line werden keine CCFL-Phänomene beobachtet.

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          Most cited references4

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

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            Countercurrent flow of air/water and steam/water through a horizontal perforated plate

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              Two-phase countercurrent flow in a model of a pressurized water reactor hot leg

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                Author and article information

                Journal
                kt
                Kerntechnik
                Carl Hanser Verlag
                0932-3902
                2195-8580
                2012
                : 77
                : 6
                : 442-448
                Affiliations
                1 E-mail: junghua1984@ 123456gmail.com , Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013, Taiwan (R.O.C.)
                2 E-mail: htlin@ 123456iner.gov.tw
                3 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.)
                4 E-mail: ckshih@ 123456ess.nthu.edu.tw , Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013, Taiwan (R.O.C.)
                Article
                KT110289
                10.3139/124.110289
                b9c5e923-792e-43a8-b413-fd03b5a626c3
                © 2012, Carl Hanser Verlag, München
                History
                : 31 July 2012
                Page count
                References: 18, Pages: 7
                Categories
                Technical Contributions/Fachbeiträge

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

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