包络18个月换料和年度换料的压水堆灵活性燃料管理研究

Research on Flexible Fuel Management for Pressurized Water Reactor Incorporating 18-month and Annual Refueling

  • 摘要: 我国可再生能源发电有了突破性发展,核电厂参与电网调峰需求迫切,固定换料周期的年度或18个月燃料管理模式难以适应当前核电厂变化的发电需求。本文基于CPR1000机组核电厂,提出了一种灵活性燃料管理策略,包络了可长期独立运行且能根据需要切换的年度换料和18个月换料燃料管理模式,完成了关键中子学参数限值分析和事故安全评价。结果表明,燃料管理方案覆盖了309~549 EFPD范围,满足了年度和18个月换料的多样化能量需求,堆芯设计、安全分析关键参数计算结果与目前18个月换料相似,满足相关安全限值要求。灵活性燃料管理对核电厂系统和设备影响小,具备工程实施的可行性,并具有显著的经济性。

     

    Abstract: China has achieved significant breakthroughs in both the newly installed capacity and power generation of renewable energy, thus urgently necessitating nuclear power plants to participate in grid peak regulation. However, the traditional fuel management models, which adhere to fixed annual or 18-month refueling cycles, lack flexibility and are unable to adapt to the changing power generation demands of modern nuclear power plants. Enhancing the flexible fuel management in nuclear power plants has emerged as a common concern within the industry. In this paper, a flexible fuel management strategy that encompasses both annual and 18-month refueling modes was introduced. Each mode was capable of operating independently for extended periods and could be seamlessly switched between based on the specific needs of the nuclear power plant. In the flexible fuel management strategy, the 18-month refueling mode incorporated a dual-enrichment core loading scheme, consisting of fuel assemblies with enrichment levels of 4.45% and 4.95%, to cater to the plant’s need for extended cycle lengths during periods of ample power generation demand. Conversely, the annual refueling mode employed a dual-enrichment core configuration of 4.0% and 4.45% enrichments, tailored to accommodate shorter cycle lengths in scenarios of insufficient power generation. The characteristic of the transitional cycle between these two modes was a substantial utilization of components with an intermediate enrichment of 4.45%, facilitating a rapid and seamless transition. Based on the designed fuel management schemes, comprehensive research was conducted, encompassing general fuel management practices, key neutronic parameters, and accident safety analysis and evaluation. The results demonstrate that the flexible fuel management scheme effectively spans the range of 309 EFPD to 549 EFPD, efficiently addressing the diverse energy requirements for both annual and 18-month refueling cycles, thereby significantly enhancing fuel management flexibility. Notably, the core design and safety analysis parameters closely align with those observed in the current 18-month refueling practice, ensuring compliance with pertinent safety thresholds. Remarkably, the successful utilization of a unified set of neutronic parameters to encapsulate both fuel management modes streamlines the safety evaluation process during both engineering design and refueling design stages. Furthermore, flexible fuel management exhibits minimal impact on nuclear power plant systems and equipment, rendering it a viable option for engineering implementation. Compared to the reference power plant, this scheme improves fuel management flexibility, reduces fuel loss caused by early shutdown, increases average discharge burnup, and introduces the cost of fuel management improvements required to meet changes in power generation demand. Therefore, the economic benefits are significant.

     

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