COSI6: A Tool for Nuclear Transition Scenario Studies and Application to SFR Deployment Scenarios with Minor Actinide Transmutation
COSI6: A Tool for Nuclear Transition Scenario Studies and Application to SFR Deployment Scenarios with Minor Actinide Transmutation
复制标题
COSI6：核转变情景研究的工具以及在具有小锕系元素嬗变的恒星形成率部署情景中的应用
DOI：
10.13182/nt15-20
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发表时间：
2015
影响因子：
1.5
通讯作者：
C. Chabert
中科院分区：
文献类型：
--
作者：
C. Coquelet;M. Tiphine;G. Krivtchik;D. Freynet;Camille Cany;R. Eschbach;C. Chabert
摘要核系统由不同燃料的反应堆和循环设施（浓缩厂、制造厂、后处理厂等）组成，是复杂的，并在不断发展。自1985年以来，CEA一直在开发模拟软件COSI，以研究核舰队演变的不同轨迹，并为决策者提供技术要素。阐述了COSI的基本原理，包括数据集的典型组成。为了尽可能准确地评估材料的同位素组成，COSI中实现了几个物理模型。其中主要的演化计算和等效模型，进行了详细描述。法国压水反应堆（PWR）的历史核舰队，直到2010年进行的COSI验证的练习，以及传播的输入不确定性COSI结果的方法。为了说明COSI的可能性，在法国废物管理法的框架内研究的不同方案的结果进行了讨论。这些方案的目的是评估钠冷快堆（SFR）部署的可行性，以更新法国PWR舰队在不同的时间尺度和分析的成本和效益的不同选项的次锕系元素（MA）的分区和嬗变。SFR部署对循环设施的影响，如制造厂，乏燃料储存，和后处理厂最小化。就裂变材料的可得性而言，SFR的部署似乎是可行的，但需调整后处理前的燃料冷却时间或SFR增殖增益。轻微的锕系元素嬗变均匀模式MA稀释的核心）和嬗变的异质模式（在MA轴承毯）进行了比较，不仅根据其对循环设施和最终的废物的影响，但也根据其库存的减少。由于在燃料中添加MA，新鲜燃料热功率和乏燃料衰变热的增加被量化。所有的MA（镅，镎，铥）和仅镅的嬗变的情况是有区别的。替代方案进行了探讨，以克服与每个选项相关的挑战：减少最大MA含量的新鲜SFR燃料的情况下，均匀的嬗变和减少临时MA存储的情况下，异构嬗变。
Abstract Nuclear systems, composed of reactors with varied fuel and cycle facilities (enrichment plant, fabrication plant, reprocessing plant, etc.), are complex and in constant evolution. Since 1985, the CEA has been developing the simulation software COSI to study different trajectories of nuclear fleet evolution and provide technical elements to decision makers. The principle of COSI, including the typical composition of the data set, is exposed. To evaluate as accurately as possible the isotopic compositions of materials, several physical models are implemented in COSI. The main ones, the evolution calculation and the equivalence models, are described in detail. An exercise of validation of COSI carried out on the French pressurized water reactor (PWR) historical nuclear fleet until 2010 is also presented, as well as a methodology for propagation of input uncertainties on COSI results. To illustrate the possibilities of COSI, the results of different scenarios studied in the framework of the French Act for Waste Management are discussed. The objective of these scenarios is to evaluate the feasibility of sodium-cooled fast reactor (SFR) deployment to renew the French PWR fleet on different timescales and to analyze the costs and the benefits of different options of minor actinide (MA) partitioning and transmutation. The impacts of SFR deployment on cycle facilities such as the fabrication plant, the spent fuel storage, and the reprocessing plant are minimized. The SFR deployment appears to be feasible with regard to fissile material availability, with an adaptation of fuel cooling time before reprocessing or of SFR breeding gain. Minor actinide transmutation in homogeneous mode MA diluted in core) and transmutation in heterogeneous mode (in MA-bearing blankets) are compared not only according to their impacts on cycle facilities and on ultimate waste but also according to the reduction of their inventories. The increases in fresh fuel thermal power and spent fuel decay heat due to the addition of MAs in fuels are quantified. The cases of transmutation of all MAs (americium, neptunium, and curium) and of americium only are distinguished. Alternative scenarios are explored to overcome the challenges associated with each option: reduction of the maximal MA content in fresh SFR fuel in the case of homogeneous transmutation and reduction of interim MA storage in the case of heterogeneous transmutation.