Lashkari A, Khalafi H, Kazeminejad H
Reactors and Accelerators Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), Tehran 14399-51113, Iran.
Ann Nucl Energy. 2013 May;55(100):265-271. doi: 10.1016/j.anucene.2012.12.001.
In this work, kinetic parameters of Tehran research reactor (TRR) mixed cores have been calculated. The mixed core configurations are made by replacement of the low enriched uranium control fuel elements with highly enriched uranium control fuel elements in the reference core. The MTR_PC package, a nuclear reactor analysis tool, is used to perform the analysis. Simulations were carried out to compute effective delayed neutron fraction and prompt neutron lifetime. Calculation of kinetic parameters is necessary for reactivity and power excursion transient analysis. The results of this research show that effective delayed neutron fraction decreases and prompt neutron lifetime increases with the fuels burn-up. Also, by increasing the number of highly enriched uranium control fuel elements in the reference core, the prompt neutron lifetime increases, but effective delayed neutron fraction does not show any considerable change.
在这项工作中，已计算出德黑兰研究堆（TRR）混合堆芯的动力学参数。混合堆芯配置是通过在参考堆芯中用高浓铀控制燃料元件替换低浓铀控制燃料元件制成的。使用核反应堆分析工具MTR_PC软件包进行分析。进行了模拟以计算有效缓发中子份额和瞬发中子寿命。动力学参数的计算对于反应性和功率漂移瞬态分析是必要的。本研究结果表明，随着燃料燃耗，有效缓发中子份额降低，瞬发中子寿命增加。此外，通过增加参考堆芯中高浓铀控制燃料元件的数量，瞬发中子寿命增加，但有效缓发中子份额没有显示出任何显著变化。
