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Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes

机译:使用WIMS和CITATION代码模拟伊朗VVER-1000核反应堆的反应系数

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Reactivity coefficients analysis of the Bushehr Nuclear Power Plant (BNPP), VVER-1000, at nominal conditions is carried out during its first operational cycle where we used WIMS and CITATION codes in our theoretical studies. Modelling of all rods (including fuel rods, control rods, burnable and non-burnable poison rods) and channels (including central guiding channel, central channel and reactor perimeters) is carried out using the WIMS code. Moreover, modelling of the fuel assemblies and reactor core is completed using the CITATION code. The multi-group constants generated by WIMS for different fuel configurations are fed into CITATION. The multi-group constants for fuel assemblies are obtained from the flux distribution calculated by the code. Then by putting fuel assemblies together to make up the core, and using the calculated constants, the core multiplication factor is calculated for different conditions. A FORTRAN 90 program is written to link the WIMS and CITATION codes and facilitate their numerous executions. Our calculated reactivity coefficients are comparable with the plant's FSAR.
机译:在标称条件下,对布什尔核电站(BNPP)VVER-1000的反应系数分析是在其第一个运行周期内进行的,在该周期中我们在理论研究中使用了WIMS和CITATION代码。使用WIMS代码对所有棒(包括燃料棒,控制棒,可燃和不可燃毒药棒)和通道(包括中央引导通道,中央通道和反应堆周长)进行建模。此外,燃料组件和反应堆堆芯的建模使用CITATION代码完成。 WIMS为不同的燃料配置生成的多组常量被送入CITATION。燃料组件的多组常数是从代码计算出的通量分布中获得的。然后,通过将燃料组件组合在一起组成堆芯,并使用计算出的常数,针对不同条件计算堆芯倍增系数。编写一个FORTRAN 90程序来链接WIMS和CITATION代码,并促进它们的大量执行。我们计算出的反应系数可与工厂的FSAR相媲美。

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