This article presents the current state of knowledge on beryllium, its nuclear properties and reactions, based on experience gathered in multiple material testing reactors or beryllium manufacturers. The main focus is given to reactions of high importance due to their impact on the reactor's operation and safety, in a particular buildup of both tritium and neutron absorbers - so-called poisons. Few experimental methods have been developed to assess beryllium state. A brief review is used to point out the most accurate methods used to estimate beryllium's maximum operation time and the associated impact on reactor characteristics. A neutron transmission-based measurement method is proposed as an experimental assessment of beryllium poisoning in the MARIA reactor (Poland). The neutron transmission analysis is carried out to experimentally validate the associated numerical methodology and calculation schemes. The aim is the development of an accurate, easily transposable core model, allowing for optimal use of beryllium in other MTRs such as JHR reactor.

本文基于在多个材料测试反应堆或铍制造商中积累的经验，介绍了有关铍、其核特性和反应的当前知识状态。主要关注高度重要的反应，因为它们会对反应堆的运行和安全产生影响，特别是氚和中子吸收剂（所谓的毒物）的累积。已经开发了很少的实验方法来评估铍状态。简要回顾用于指出用于估计铍最大运行时间和对反应堆特性的相关影响的最准确方法。提出了一种基于中子传输的测量方法，作为 MARIA 反应堆（波兰）铍中毒的实验评估。进行中子传输分析以通过实验验证相关的数值方法和计算方案。目标是开发准确、易于转置的堆芯模型，以便在 JHR 反应堆等其他 MTR 中优化使用铍。