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不同燃料循环方案的可持续性与经济性分析

丁文杰 黄欢 戴涛 郭海兵

丁文杰, 黄欢, 戴涛, 等. 不同燃料循环方案的可持续性与经济性分析[J]. 强激光与粒子束, 2019, 31: 056007. doi: 10.11884/HPLPB201931.190013
引用本文: 丁文杰, 黄欢, 戴涛, 等. 不同燃料循环方案的可持续性与经济性分析[J]. 强激光与粒子束, 2019, 31: 056007. doi: 10.11884/HPLPB201931.190013
Ding Wenjie, Huang Huan, Dai Tao, et al. Sustainability and economy analysis of different fuel cycle options[J]. High Power Laser and Particle Beams, 2019, 31: 056007. doi: 10.11884/HPLPB201931.190013
Citation: Ding Wenjie, Huang Huan, Dai Tao, et al. Sustainability and economy analysis of different fuel cycle options[J]. High Power Laser and Particle Beams, 2019, 31: 056007. doi: 10.11884/HPLPB201931.190013

不同燃料循环方案的可持续性与经济性分析

doi: 10.11884/HPLPB201931.190013
基金项目: 

国家自然科学基金项目 L172400024

详细信息
    作者简介:

    丁文杰(1990-),男,硕士,助理研究员,主要从事反应堆热工水力研究; dwjcaep@163.com

  • 中图分类号: TL249

Sustainability and economy analysis of different fuel cycle options

  • 摘要: 基于核燃料循环政策技术的成熟度,选取了一次通过循环方案(OTC)、单次复用循环方案(TTC)、快堆闭式循环方案(FRC)及混合堆闭式循环方案(HRC)四种典型的核燃料循环方案进行分析。采用平衡物质流模型对不同燃料循环方案的可持续性进行研究,基于平准化电力成本计算方法对不同方案的燃料成本和乏燃料处置成本进行分析。研究结果表明:闭式燃料循环可极大减少核废料产生; 燃料可自持的FRC方案及HRC方案可使用贫铀做燃料而不消耗天然铀; 仅考虑燃料成本和乏燃料处置成本时,HRC方案的经济性最高而TTC方案的经济性最差。
  • 图  1  OTC方案物质流计算示意图

    Figure  1.  Schematic diagram of mass flow calculation in the OTC option

    图  2  天然铀需求量与贫铀产生量

    Figure  2.  Natural uranium demand and depleted uranium production

    图  3  核废物产生量

    Figure  3.  Production of nuclear waste

    图  4  不同循环方案的平准化电力成本

    Figure  4.  Levelized cost of electricity in different cycle options

    表  1  轻水反应堆装料质量流

    Table  1.   Light water reactor loading mass flow

    nuclide mass flow/(MTHM·GWe-1·a-1)
    PWR UO2 PWR MOX/UO2
    load after cooling load after cooling
    MOX UO2 MOX UO2
    HM 19.5 18.494 5.719 13.667 5.425 12.964
    U(235U) 19.500(0.825) 18.244(0.150) 5.22 13.667 5.041 12.788
    Pu 0 0.225 0.491 0 0.343 0.157
    MA 0 0.025 0.008 0 0.04 0.02
    TRU 0 0.25 0.499 0 0.383 0.177
    FP 0 1.006 0 0 0.293 0.703
    下载: 导出CSV

    表  2  快堆装料质量流

    Table  2.   Fast reactor loading mass flow

    nuclide mass flow/(MTHM·GWe-1·a-1)
    fast breeder reactor fast burner reactor
    CR=1.23 CR=0 CR=0.5 CR=0.75 CR=1
    load after cooling load after cooling load after cooling load after cooling load after cooling
    HM 14.84 14.01 2.78 1.906 6.194 5.324 8.203 7.327 11.19 10.34
    TRU 1.287 1.507 2.741 1.866 2.064 1.667 1.74 1.575 1.552 1.571
    U 13.52 12.47 0.039 0.04 4.13 3.647 6.463 5.752 9.64 8.763
    FP 0 0.831 0 0.874 0 0.87 0 0.876 0 0.857
    Pu 1.287 1.507 - - - - - - - -
    下载: 导出CSV

    表  3  前端燃料单元的价格

    Table  3.   Price of units of front-end fuel

    unit reference value/($·kgHM-1)
    natural uranium 100
    depleted uranium 10
    conversion 10a
    concentration 140b
    UOX fabrication 258c
    MOX fabrication 2 400
    fabrication of fast reactor fuel 2 400
    fabrication of hybrid reactor fuel 30d
    Notes:
    a:The conversion price of recycled uranium is about 300% of that of the natural uranium;
    b:The enrichment price of recycled uranium is about 110% of that of the natural uranium;
    c:The manufacturing price of REPUOX fuel is about 107% of that of the natural uranium;
    d:The fuel for the hybrid reactor is a plate structure and requires no fine processing, so the manufacturing cost is low, but there was no mature technology. Referring to the conversion process of recycled uranium, the manufacturing cost of the hybrid reactor fuel was set to 30 $·kgHM-1.
    下载: 导出CSV

    表  4  燃料处置单元的价格

    Table  4.   Price of units of fuel disposal

    unit reference value/($·kgHM-1)
    UOX temporary storage 200
    MOX temporary storage 200
    UOX spent fuel disposal 412
    MOX spent fuel disposal 3 130
    UOX HLW 190
    fast reactor HLW 280
    UOX reprocess 1 600
    fast reactor fuel reprocess 3 200
    simple dry processing 120a
    Notes:
    a:The cost of fuel temporary cooling and storage was included in the cost of fuel reprocessing. The hybrid reactor fuel was reprocessed every five years by the simple dry process, to remove the fission products of spent fuel using the decay heat. The process was simple and required little cost, but there was no mature technology. Referring to the price of dry storage in EPRI, the price of simple dry process was set to 120 $·kgHM-1
    下载: 导出CSV
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出版历程
  • 收稿日期:  2019-01-15
  • 修回日期:  2019-02-24
  • 刊出日期:  2019-05-15

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