为稳定法国的乏燃料库存,向压水堆机群提供了多种回收方案

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2021-01-01 DOI:10.1051/epjn/2021022
F. Courtin, Camille Laguerre, Philippe Miranda, C. Chabert, G. Martin
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引用次数: 2

摘要

进行核情景研究以探索核舰队可能演变的影响。由CEA开发的核燃料循环模拟工具COSI用于模拟这些动态情景,并在铀和钚管理、燃料后处理和废物产生方面对它们进行评价。近年来,方案的重点是从目前的法国核舰队过渡到部署SFR。然而,法国的多年度能源规划最近将这项技术的部署推迟到21世纪下半叶。研究了压水堆钚管理的备选方案,以稳定乏燃料总库存。MIX概念基于均质燃料组件,其中燃料棒由混合了浓缩铀的钚组成。在这项研究中,模拟了从目前的法国舰队到EPR™舰队的过渡。考虑了未来EPR™机队的两种功率容量。在EPR™机群中逐步部署燃料多重回收,以稳定所有乏燃料和钚库存。由于EPR™中的ERU燃料批次,天然铀的消耗也最小化。结果与压水堆中钚和铀的单一回收进行了比较。
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Pu multi-recycling scenarios towards a PWR fleet for a stabilization of spent fuel inventories in France
Nuclear scenario studies are performed to explore the impact of possible evolutions of nuclear fleets. The nuclear fuel cycle simulation tool COSI, developed by CEA, is used to model these dynamic scenarios and to evaluate them with respect to uranium and plutonium management, fuel reprocessing and waste production. In recent years, scenarios have focused on transitions from the current nuclear French fleet to a deployment of SFR. However, the French Multi-annual Energy Planning has recently postponed the deployment of this technology to the second half of the 21st century. Alternative solutions of plutonium management in PWR are investigated to stabilize total inventories of spent nuclear fuels. The MIX concept is based on homogeneous fuel assemblies where fuel rods are composed of plutonium blended with enriched uranium. In this study, a transition from the current French fleet to an EPR™ fleet is simulated. Two power capacities of the future EPR™ fleet are considered. A progressive deployment of fuel multi-recycling in the EPR™ fleet is implemented to enable stabilization of all spent fuels and plutonium inventories. Natural uranium consumption is also minimized thanks to ERU fuel batches in EPR™. Results are compared with plutonium and uranium mono-recycling in a PWR fleet.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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