重型反射层对堆芯中子学参数的影响
The effect of heavy reflector on neutronic parameters of core
AI总结：
本文研究重型VVER-1000围板对堆芯临界性的影响，通过LR-0反应堆实验验证围板冷却水的强中子吸收效应，发现IAEA新版56Fe截面计算结果比ENDF/B-VIII.0库更贴合实验，可为铁截面验证提供数据支撑。
摘要：
反应堆围板是核反应堆中固定燃料组件在堆芯内位置的重要部件，主要类型分为轻型围板和重型围板。轻型围板多为钢板结构，外侧空间充水；重型围板多为锻钢构件。两种设计各有优劣：轻型围板无需解决空泡肿胀问题，但中子经济性不理想；重型围板中子经济性良好，但存在空泡肿胀问题。本文研究重型VVER-1000围板对临界性的影响。实验采用由6组燃料组件构成的明确堆芯，将其移入位于LR-0反应堆的VVER-1000内部构件模拟器中进行临界性测量。实验证实，围板冷却通道内的充水具有强中子吸收效应。使用ENDF/B-VIII.0库计算得到的keff显著低于实验值，而采用IAEA（INDEN合作组）最新评估的56Fe截面计算的结果与实验吻合度更好。总体而言，本文给出的结果适用于铁截面的验证。
英文摘要：
The reactor baffle is an important component of a nuclear reactor that fixes the location of the fuel assembly in the reactor core. The main types of baffles are called light or heavy. The light baffle has mostly the form of steel plates with outer space filled by water, and the heavy baffle is mostly a forged steel element. Both concepts have advantages as well as disadvantages. In the case of the light baffle, one does not need to solve the issue of void swelling, but the neutron economy is not ideal, while the heavy baffle has a good neutron economy, but void swelling is an issue. This paper deals with the effect of the heavy VVER-1000 baffle on criticality. Criticality was measured using a well-defined core composed of 6 fuel assemblies moved to a simulator of the VVER-1000 internals, which is located at the LR-0 reactor. The experiments confirm the fact that the water filling the cooling channels in the baffle has a strong neutron absorbing effect. The keff calculated using the ENDF/B-VIII.0 library significantly underpredicts the experiment, whereas calculations using a new evaluation of 56Fe by the IAEA (INDEN collaboration) give a better agreement. Generally, the presented results are suitable for validation of iron cross sections.
机构、总结、中文摘要均由AI分析而来，可能存在错误，请以论文正文为准。
