Wainwright Haruko M, Christiaen Chloe, Atz Milos, Tchakerian John Sebastian, Yu Jiankai, Ridley Gavin Keith, Shirvan Koroush
Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, USA.
Department of Civil and Environmental Engineering, Massachusetts Institute of Technology, Cambridge, USA.
Sci Rep. 2024 Nov 6;14(1):26904. doi: 10.1038/s41598-024-77255-3.
This study presents a multidisciplinary reactor-to-repository framework to compare different advanced reactors with respect to their spent nuclear fuel (SNF) disposal. The framework consists of (1) OpenMC for simulating neutronics, fuel depletion, and radioactive decays; (2) NWPY for computing the repository footprint given the thermal constraints; and (3) PFLOTRAN for simulating radionuclide transport in the geosphere to quantify the repository performance and environmental impact. We first perform the meta-analysis of past comparative analyses to identify the factors that led previously to their inconsistent conclusions. We then demonstrate the new framework by comparing five reactor types. Our analysis highlights the granularity and the specificities of each reactor and fuel type so that we should avoid making sweeping conclusions about advanced reactor SNF. Significant findings are that (1) the repository footprint is neither linearly related to SNF volume nor to decay heat, due to the repository's thermal constraint (2), fast reactors have significantly higher I-129 inventory, which is often the primary dose contributor, and (3) the repository performance primarily depends on the waste forms. The TRISO-based reactors, in particular, have significantly higher SNF volumes compared to the others but result in smaller repository footprints and lower peak dose rates. The open-source framework ensures proper multidisciplinary connections between reactor simulations and environmental assessments, as well as the transparency/traceability required for such comparative analyses. It aims to support reactor designers, repository developers, and policymakers in evaluating the impact of different reactor designs, with the ultimate goal of improving the sustainability of nuclear energy systems.
本研究提出了一个多学科的从反应堆到储存库的框架,以比较不同先进反应堆在乏核燃料(SNF)处置方面的情况。该框架包括:(1)用于模拟中子学、燃料耗尽和放射性衰变的OpenMC;(2)用于在给定热约束条件下计算储存库占地面积的NWPY;以及(3)用于模拟地球圈层中放射性核素迁移以量化储存库性能和环境影响的PFLOTRAN。我们首先对过去的比较分析进行元分析,以确定先前导致其结论不一致的因素。然后,我们通过比较五种反应堆类型来展示这个新框架。我们的分析突出了每种反应堆和燃料类型的粒度和特殊性,因此我们应该避免对先进反应堆的乏核燃料做出一概而论的结论。重要发现包括:(1)由于储存库的热约束,储存库占地面积与乏核燃料体积和衰变热均无线性关系;(2)快堆的碘-129存量显著更高,而碘-129通常是主要的剂量贡献者;(3)储存库性能主要取决于废物形式。特别是,基于TRISO的反应堆与其他反应堆相比,乏核燃料体积显著更大,但储存库占地面积更小,峰值剂量率更低。这个开源框架确保了反应堆模拟与环境评估之间适当的多学科联系,以及此类比较分析所需的透明度/可追溯性。其目的是支持反应堆设计者、储存库开发者和政策制定者评估不同反应堆设计的影响,最终目标是提高核能系统的可持续性。