Abstract To license the gas-cooled fast reactor design, sufficient data should be known about its safety and operation capability. The first step in deployment of the commercial GFR 2400 is to prove the design and physical parameters by its demonstrator, referred as ALLEGRO. This study summarizes sensitivity, uncertainty and similarity analyses of GFR 2400 and ALLEGRO cores utilizing standard and in-house developed codes. In the part focused on the sensitivity analyses, the in-house developed calculation scheme is compared and validated with available commercial codes for both gas-cooled fast reactor designs. The following part is aimed to estimate the uncertainty propagated from nuclear data to keff for the ALLEGRO design. The highest contributor to keff uncertainty induced by nuclear data is 239Pu fission neutron yield (nubar), due to the high sensitivity profile and inelastic scattering reaction on 238U, due to the associated large cross-section uncertainty in the energy spectra of interest. The last part is focused on the similarity assessment of both gas-cooled fast reactor designs. The results show that the ALLEGRO MOX starting core is not sufficient representation of the commercial GFR 2400 accommodating carbide fuel, therefore carbide fuel type has to be used also in the next fuel loading patterns in ALLEGRO design to demonstrate the feasibility of GFR 2400 design.

中文翻译：

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关于气冷快堆设计——具有敏感性、不确定性和相似性分析的核数据处理

摘要 要获得气冷快堆设计许可，必须了解其安全性和运行能力的足够数据。部署商用 GFR 2400 的第一步是通过其演示器（称为 ALLEGRO）来证明设计和物理参数。本研究总结了使用标准和内部开发代码对 GFR 2400 和 ALLEGRO 岩心进行的敏感性、不确定性和相似性分析。在专注于敏感性分析的部分中，内部开发的计算方案与气冷快堆设计的可用商业代码进行了比较和验证。以下部分旨在估计从核数据传播到 ALLEGRO 设计的 keff 的不确定性。由核数据引起的 keff 不确定性的最大贡献者是 239Pu 裂变中子产额 (nubar)，由于 238U 上的高灵敏度分布和非弹性散射反应，以及相关能谱中相关的大横截面不确定性。最后一部分侧重于对两种气冷快堆设计的相似性评估。结果表明 ALLEGRO MOX 起始堆芯不足以代表商业 GFR 2400 容纳碳化物燃料，因此在 ALLEGRO 设计的下一个燃料装载模式中也必须使用碳化物燃料类型，以证明 GFR 2400 设计的可行性。