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    National Tsing Hua University Institutional Repository > 原子科學院  > 工程與系統科學系 > 會議論文  >  Assessment of RELAP5/Mod3 system thermal hydraulic code using power test data of a BWR6 reactor

    Please use this identifier to cite or link to this item: http://nthur.lib.nthu.edu.tw/dspace/handle/987654321/46975

    Title: Assessment of RELAP5/Mod3 system thermal hydraulic code using power test data of a BWR6 reactor
    Authors: Lee, R.;Chiang, C.S.
    教師: 李敏
    Date: 1997
    Publisher: Atomic Energy Soc. Japan
    Relation: Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics. NURETH-8. New Horizons in Nuclear Reactor Thermal-Hydraulics
    Keywords: transient analysis
    nuclear engineering computing
    fission reactor safety
    fission reactor kinetics
    fission reactor design
    fission reactor cooling
    fission reactor core control
    Abstract: The power test data of Kuosheng nuclear power plant were used to assess RELAP5/Mod3 system thermal hydraulic analysis code. The plant employed a General Electric designed boiling water reactor (BWR6) with rated power of 2894 MWth. The purpose of the assessment is to verify the validity of the plant specific RELAP5/Mod3 input deck for transient analysis. The power tests considered in the assessment were 100% power generator load rejection, the closure of main steam isolation valves (MSIVs) at 96% power, and the trip of recirculation pumps at 68% power. The major parameters compared in the assessment were steam dome pressure, steam flow rate, core flow rate, and downcomer water level. The comparisons of the system responses predicted by the code and the power test data were reasonable which demonstrated the capabilities of the code and the validity of the input deck. However, it was also identified that the separator model of the code may cause energy imbalance problem in the transient calculation. In the assessment, the steam separators were modeled using time-dependent junctions. In the approach, a complete separation of steam and water was predicted. The system responses predicted by RELAP5/Mod3 code were also compared with those from the calculations of RETRAN code. When these results were compared with the power test data, the predictions of the RETRAN code were better than those of RELAP5/Mod3. In the simulation of 100% power generator load rejection, it was believed that the difference in the steam separator model of these two codes was one of the reason of the difference in the prediction of power test data. The predictions of RELAP/Mod3 code can also be improved by the incorporation of one-dimensional kinetic model. There was also some margin for the improvement of the input related to the feedwater control system
    URI: http://wwwsoc.nii.ac.jp/aesj/index-e.html
    Appears in Collections:[工程與系統科學系] 會議論文

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