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压水堆多堆联合堆芯装载设计技术应用研究

Application Study on the Multi-core Joint Loading Design Technique for PWRs
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摘要 在压水堆之间开展的多堆联合堆芯装载设计技术能提高堆芯装载设计的灵活性,研究其对燃料经济性和机组在燃料组件损坏情况下应对能力的影响。分析了多堆联合堆芯装载设计技术对来自其他机组燃耗过燃料组件的相容性要求。计算了燃耗过燃料组件的余热与冷却时间的关系,列出了可用于燃耗过燃料组件运输的大负荷乏燃料运输容器。分析了首循环堆芯和换料堆芯面对燃料组件损坏后堆芯装载设计的应对能力,以及在采用多堆联合堆芯装载设计技术后的应对能力改善情况。开展了多堆联合首循环堆芯装载模拟设计并分析了其经济性。研究结果表明,首循环出现燃料组件损坏的风险比后续换料堆芯大,而由全新燃料组件组成的首循环应对燃料组件损坏的能力最低;通过多堆联合堆芯装载设计技术可以把首循环转化为换料堆芯,不仅能凭借换料堆芯的设计灵活性提高应对燃料组件损坏的能力,还能节省约3.2亿元人民币的燃料费。因此,多堆联合堆芯装载设计技术能提高首循环的燃料经济性和机组面对燃料组件损坏后的应对能力。 The implementation of the multi-core joint loading design technique for PWRs can enhance the flexibility of the core loading design, the study is to find the effects of the technique for the fuel economy and the capability to solve the problem of fuel assembl y damage. The compatibility requirement for the burned fuel assemblies from other units are analyzed for the multi-core joint loading design technique. The residual powers of the burned fuel assemblies as a function of the cooling time are analyzed, and the available transport casks with large thermal load for the transportation of the burned fuel assemblies during applicating the multi-core joint loading design technique are listed. The capability of the core loading design for solving the problem of fuel assembly damage is analyzed for the first core and the reloaded core, and the improvement of the capability is analyzed after applicating the multi-core joint loading design technique. The first core simulation design applicating multi-core joint loading design technique and its fuel economy analysis have been done. It found that the risk of fuel assembly damage in the first core is bigger than that of the following reloaded cores, and the capability of solving the problem of fuel assembly damage for the first core only loading new fuel assemblies is worst;the first core can be transformed into the reloaded core by applicating the multi-core joint loading design technique, which can improve the capability of solving the problem of fuel assembly damage for the first core by the design flexibility of the reload core and save about 320 million yuan of fuel cost. Thus, the multi-core joint loading design technology can improve the fuel economy of the first core and the capability of solving the problem of fuel assembly damage.
作者 马兹容 MA Zirong(Reactor Engineering Dept,Hualong Nuclear Power Technology Co.,Ltd.,Beijing 100036,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第2期266-273,共8页 Nuclear Science and Engineering
关键词 堆芯装载 首循环 乏燃料运输容器 Core loading First cycle Transport cask for spent fuel
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  • 1付卓亚,卢铁忠,顾颖宾,等.江苏核电有限公司中长期发展战略与规划(2008-2020)[R].连云港:江苏核电有限公司,2008.
  • 2付亚卓,卢铁忠,顾颖宾,等.江苏核电有限公司第一个五年发展规划(2008-2012)[R].连云港:江苏核电有限公司,2008.
  • 3马灵,于玲,帅希建,等.田湾核电站长周期换料经济可行性研究报告[R].连云港:江苏核电有限公司,2009.
  • 4张向京,沈红,李祝三,等.1、2号机组换料检修十年规划(2009-2018)[R].连云港:江苏核电有限公司,2008.
  • 5张向京,高顺龙,卢铁忠,等.1、2号机组换料检修十年规划(2011-2020)[R].连云港:江苏核电有限公司,2010.
  • 6江苏省电力公司办公室.关于编制2012年发电机组检修计划的通知[R].南京:江苏省电力公司,2011.
  • 7ALESHIN S. Calculation of the neutron physical characteristics of the 5 8 fuel cycles unit 1 TNPP taking into account of six pilot TVS-2M loading in the fifth cycle[R]. Moscow: NRC Kurchatov Institute, 2009.
  • 8李文双,姚进国,王建瑜,等.田湾核电站1、2号机组长周期燃料循环和新型燃料组件引入专项堆芯燃料管理技术服务[R].连云港:江苏核电有限公司,2011.
  • 9ALESHIN S. Calculation of neutron physics characteristics of transient fuel cycles, beginning from the 8'h fuel cycle, with reaching the equilib rium fuel cycle of TNPS, units lI2[R]. Mos- cow: NRC Kurchatov Institute, 2011.
  • 10BYCHKOVA N. Fuel management report for TNPS unit 1 cycle 2[R] Moscow: NRC Kurchatov Institute, 2007.

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