Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels

M. Marek, J. Rataj, S. Vandlík
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Abstract

The paper summarizes the attenuation coefficient of the neutron fluence with E > 0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units. The attenuation coefficient is possible to evaluate directly only by using the retro-dosimetry, based on a combination of the measured activities from the weld sample and concurrent ex-vessel measurement. The available neutron fluence attenuation coefficients (E > 0.5 MeV), calculated and measured at a mock-up experiment simulating the VVER-440-unit conditions, vary from 3.5 to 6.15. A similar situation is used for the calculations and mock-up experiment measurements for the VVER-1000 RPV, where the attenuation coefficient of the neutron fluence varies from 5.99 to 8.85. Because of the difference in calculations for the real units and the mock-up experiments, the necessity to design and perform calculation benchmarks both for VVER-440 and VVER-1000 would be meaningful if the calculation model is designed adequately to a given unit.
VVER-440和VVER-1000压力容器衰减系数的比较
本文总结了在模拟实验中测量和(或)计算的vodo-vodyanoi energetichesky reactor (VVER)反应堆类型以及运行中的核电站(NPP)机组中,E > 0.5 MeV的中子通量通过反应堆压力容器的衰减系数。衰减系数可以通过使用反剂量法直接评估,该方法基于焊接样品的测量活度和同时进行的容器外测量。在模拟vver -440单元条件的模拟实验中计算和测量的可用中子通量衰减系数(E > 0.5 MeV)在3.5 ~ 6.15之间变化。在VVER-1000 RPV的计算和模拟实验测量中也使用了类似的情况,其中中子通量的衰减系数从5.99到8.85不等。由于实际装置和模拟实验的计算差异,如果计算模型设计得足够适合给定的装置,那么为VVER-440和VVER-1000设计和执行计算基准的必要性将是有意义的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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