AI 中文总结
研究针对反应堆辐射屏蔽应用中源区远大于探测器区的情况，提出处理核反应多样性创建完整伴随核数据库的方法，以用于TRIPOLI-5，通过基准配置验证策略并与正向模拟比较。
AI 中文摘要
与反应堆设计相关的辐射屏蔽应用中，源区（堆芯）比探测器区（剂量计）大得多，求解伴随输运方程可显著提高蒙特卡罗模拟效率。伴随粒子从探测器产生，反向飞行和碰撞并在源区积累计数。采样伴随碰撞事件关键前提是准备伴随核数据。本文提出通用方法处理现代中子数据评估中核反应多样性，最终创建完整伴随核数据库，这是在TRIPOLI-5中实现伴随采样方案的基石。基于重轻核素混合物连续能量基准配置验证该策略，并与标准正向蒙特卡罗模拟结果比较。
英文摘要
Radiation shielding applications related to reactor design typically involve situations where the source region (the core) is much larger than the detector region (a dosimeter). In such cases, the efficiency of Monte Carlo simulation might be significantly increased by solving the adjoint transport equation: adjoint particles are born from the detector, undergo adjoint ('reversed') flights and collisions, and accumulate their tallies in the source region. A key prerequisite to sample the adjoint collision events is the preparation of adjoint nuclear data. In this work, we propose a general method able to handle the diversity of nuclear reactions available in modern neutron data evaluations, and ultimately create a full adjoint nuclear data library. This is a stepping stone in view of implementing adjoint sampling schemes in TRIPOLI-5 __ , the next-generation Monte Carlo code developed by CEA and ASNR. We validate this strategy based on a relevant continuous energy benchmark configuration involving mixtures of heavy and light nuclides, and we compare our results to those obtained by standard forward Monte Carlo simulations.
