Lead is an important material, both for fusion or fission reactors. The cross sections of natural lead should be validated because lead is a main component of lithium-lead modules suggested for fusion power plants and it directly affects the crucial variable, tritium breeding ratio. The presented study discusses a validation of the lead transport libraries by dint of the activation of carefully selected activation samples. The high emission standard ²⁵²Cf neutron source was used as a neutron source for the presented validation experiment. In the irradiation setup, the samples were placed behind 5 and 10 cm of the lead material. Samples were measured using a gamma spectrometry to infer the reaction rate and compared with MCNP6 calculations using ENDF/B-VIII.0 lead cross sections. The experiment used validated IRDFF-II dosimetric reactions to validate lead cross sections, namely ¹⁹⁷Au(n, 2n)¹⁹⁶Au, ⁵⁸Ni(n,p)⁵⁸Co, ⁹³Nb(n, 2n)^92mNb, ¹¹⁵In(n,n')^115mIn, ¹¹⁵In(n,γ)^116mIn, ¹⁹⁷Au(n,γ)¹⁹⁸Au and ⁶³Cu(n,γ)⁶⁴Cu reactions. The threshold reactions agree reasonably with calculations; however, the experimental data suggests a higher thermal neutron flux behind lead bricks. The paper also suggests ²⁵²Cf isotropic source as a valuable tool for validation of some cross-sections important for fusion applications, i.e. reactions on structural materials, e.g. Cu, Pb, etc.

铅是一种重要的材料，无论是用于聚变反应堆还是裂变反应堆。应验证天然铅的横截面，因为铅是建议用于聚变发电厂的锂铅模块的主要成分，它直接影响关键变量氚增殖率。所提出的研究讨论了通过激活精心挑选的激活样本来验证先导转运库。高排放标准²⁵²Cf 中子源用作所提出的验证实验的中子源。在辐照装置中，样品放置在 5 厘米和 10 厘米的铅材料后面。使用伽马光谱法测量样品以推断反应速率，并与使用 ENDF/B-VIII.0 铅横截面的 MCNP6 计算进行比较。该实验使用经过验证的 IRDFF-II 剂量反应来验证铅横截面，即¹⁹⁷ Au(n, 2n) ¹⁹⁶ Au, ⁵⁸ Ni(n,p) ⁵⁸ Co, ⁹³ Nb(n, 2n) ^92m Nb, ¹¹⁵ In(n ,n') ^115m In, ¹¹⁵ In(n,γ) ^116m In, ¹⁹⁷ Au(n,γ) ¹⁹⁸Au 和⁶³ Cu(n,γ) ⁶⁴ Cu 反应。阈值反应与计算合理地一致；然而，实验数据表明铅砖后面的热中子通量更高。该论文还建议将²⁵² Cf 各向同性源作为一种有价值的工具，用于验证对聚变应用很重要的一些横截面，即对结构材料（例如 Cu、Pb 等）的反应。