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題名 | Simulation of Leu-Mtr Transients Under Reactivity Insertion and Loss-of-Flow Conditions=低濃化鈾材料試驗反應器在加入反應度與喪失水流條件下之暫態模擬研究 |
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作者 | Iqbal,Masood; Mirza,Nasir M.; Mirza,Sikander M.; |
期刊 | 核子科學 |
出版日期 | 19980400 |
卷期 | 35:2 1998.04[民87.04] |
頁次 | 頁81-90 |
分類號 | 449.43 |
語文 | chi |
關鍵詞 | 低濃化鈾材料試驗反應器; 反應度; 喪失水流條件; 暫態模擬; Computer simulations; MTR transients; Void reactivity coefficient; |
英文摘要 | A series of experiments have been careeied out for the measurement of various parameters in a typical MTR type LEU-fueled core including the control rod worth by the inverse kinetics method, the control rod drop time, and the coolant temperature coefficients of reactivity. Using these experimentally measured parameters and the spatial neutron flux profiles reported in our previous work, the behaviour of the LEU core has been simulated for various transients. These simulations were done with the PARET code using the step- and rampreactivity insertions and slow- & fast- loss of flow cases. The compariosn of the results obtained by using experimentally measured values of various parameters, with the earlier benchmark studies for the LEU-MTR cores, shows significant differences in the peak power levels and in the peak temperature values. Due to 20% lower values of the temperature coefficients for this core, up to 11% higher peak power values have been found for transients initiated by $1.5/0.5 s ramps. The PARET code predicts the values of temperatures well within the safe limits throughout the core even for the maximum reactivity insertion transient due to the positive reactivity coefficient of the central flux trap region. In the natural convection cooling regime, the NATCON code predicts temperatures below the incipient boiling level for reactor power levels up to 600 kW. |
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