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Global actinides management scenarios: transition from Gen II/Gen III to Gen IV systems - Case of the french fleet

机译:全球Aptimides管理情景:从II / Gen III到IV Systems的转换 - 法国舰队的情况

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In France, the current management of spent fuels consists in their processing and in recycling the interim Plutonium inform of MOX fuel in 20 PWRs (900 MWe). This management enables reducing the storage capacity for the spent fuels, and reducing the quantity and radiotoxicity of ultimate waste, presently consisting of fission products and minor actinides solidified in the form of highly resistant long-lasting glass matrices. In the perspective of possibly eliminating in the future the minor actinides, that represent the long-life radiotoxic component of today's vitrified waste, a basic and physically optimal scenario is presented, which foresees the partitioning of those minor actinides and their recycling in the 4th generation fast neutron systems, having the intrinsic capability of fissioning all the actinides. This paper presents analysis of the transition between the current fuel cycle of PWRs, which consists in a single stage of Plutonium recycling, and that of the 4th generation systems which comprise multiple recycling of all the actinides: Uranium, Plutonium and Minor Actinides. Following a physical analysis of the respective potential of the fast neutron or thermal neutron spectra for transmutation, we examine, based on the same set of assumptions, the consequences of the date of deployment of the 4th generation systems and the merits of the scenarios for the temporary recycling in PWR of Plutonium waiting the global recycle of all of the actinides in the 4th generation systems. In the perspective of the deployment of a first series of 4th generation systems in 2030-2040, a global actinide management for the back end of the PWR cycle is considered, including the partitioning of the minor actinides. If ever the deployment of the 4th generation systems would be postponed, the aforementioned strategy would still be possible and extremely advantageous due to the capability of fast neutron systems to recycle the transuranium elements (Plutonium and minor actinides) produced by the PWRs during the 21st century.
机译:在法国,目前的废弃燃料管理包括在20 PWR(900 MWE)中回收艾灸燃料的临时钚通知。该管理能够降低花费燃料的储存能力,并降低最终废物的数量和无毒毒性,目前由裂变产物和以高耐久的长玻璃基质形式固化的次阳光亢进。在未来可能消除的视角下,代表当今玻璃化废物的长寿毒毒性成分,提出了一种基本和物理上最佳情景,这预计将在第四代中分配那些轻微的散落物及其再循环快节奏系统,具有裂变所有缺散物的内在能力。本文介绍了PWR的当前燃料循环之间的过渡,这由钚回收的单个阶段组成,第4阶段系统的阶段组成,包括所有散曲面的多次再循环:铀,钚和轻微的散发物。在对嬗变的快节中子或热中子谱的相应电位的物理分析之后,我们基于同一组假设,这是第四代系统部署日期的后果和方案的优点临时回收钚PWR等待第四代系统中所有散落物的全球回收。在2030-2040的第一系列第4代系统的部署的角度下,考虑了PWR周期的后端的全球非普通管理管理,包括次要浮雕的分区。如果推迟第四代系统的部署,则由于快速中子系统再循环在21世纪的PWR生产的经含量元素(钚和较小的浮雕)的能力,仍然可能且非常有利的策略。

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