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BWR-HD: AN OPTIMIZED BOILING WATER REACTOR WITH HIGH POWER DENSITY

机译:BWR-HD:高功率密度的优化沸腾水反应器

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摘要

Increasing the economic competitiveness of nuclear energy is vital to its future. One way to reduce the cost of the plant is by extracting more power from the same volume. A scoping study is conducted to maximize the power density in boiling water reactors (BWRs) under the constraints of using fuel with traditional materials and cylindrical geometry, and enrichments below 5% to enable its licensability with no changes to present facilities. An optimization search over all other design parameters yields a BWR with high power density (BWR-HD) at a power level of 5000 MW (thermal), equivalent to a 26% uprated Advanced BWR (ABWR), the most recently built version of BWR. The BWR-HD utilizes about the same number of wider fuel assemblies, with 16 ×16 pin arrays and 35% shorter active fuel than the 10×10 assemblies of the ABWR. The fuel rod diameter and pitch are also reduced to just over 70% of the ABWR values. Thus, it is possible to increase the power density and specific power by 65% while maintaining the nominal ABWR minimum critical power ratio margin. The optimum core pressure is found to be the same as the current 7.2 MPa. The core exit quality is increased to 19% from the ABWR nominal exit quality of 15%. The pin linear heat generation rate is 20% lower, and the core pressure drop and mass of uranium are 30% lower. The BWR-HD's fuel, modeled with FRAPCON 3.4, showed similar performance to the ABWR pin design. This results in 20% reduced operations and maintenance and capital costs per unit energy, but total fuel cycle cost similar to that of the 18-month ABWR fuel cycle.
机译:增强核能的经济竞争力对其未来至关重要。降低工厂成本的一种方法是通过从相同体积中提取更多电力。进行范围界定研究,以在使用具有传统材料和圆柱形几何形状的燃料的约束下,使沸水反应堆(BWR)的功率密度最大化,并使其浓缩度低于5%,以使其许可性不变,而无需更改现有设施。通过对所有其他设计参数进行优化搜索,可以得到功率密度为5000 MW(热)的高功率密度(BWR-HD)BWR,相当于最新制造的BWR版本的先进BWR(ABWR)提升了26%。 。与ABWR的10×10组件相比,BWR-HD使用大约相同数量的较宽的燃料组件,具有16×16的销钉阵列,有效燃料短35%。燃料棒的直径和节距也减小到ABWR值的70%以上。因此,可以在保持标称ABWR最小临界功率比裕度的同时将功率密度和比功率提高65%。发现最佳核心压力与当前的7.2 MPa相同。堆芯出口质量从ABWR标称出口质量15%提高到19%。销的线性发热率降低20%,堆芯压降和铀质量降低30%。以FRAPCON 3.4建模的BWR-HD燃料显示出与ABWR引脚设计相似的性能。这样可以减少20%的运行和维护成本以及每单位能源的资本成本,但总的燃料循环成本与18个月的ABWR燃料循环相似。

著录项

  • 来源
    《Nuclear Technology》 |2013年第3期|261-273|共13页
  • 作者

    KOROUSH SHIRVAN; MUJID KAZIMI;

  • 作者单位

    Massachusetts Institute of Technology, Department of Nuclear Science and Engineering Center for Advanced Nuclear Energy Systems, 77 Massachusetts Avenue, Cambridge Massachusetts 02139;

    Massachusetts Institute of Technology, Department of Nuclear Science and Engineering Center for Advanced Nuclear Energy Systems, 77 Massachusetts Avenue, Cambridge Massachusetts 02139;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    high-power boiling water reactor; reactor design; optimization;

    机译:大功率沸水反应堆;反应堆设计;优化;
  • 入库时间 2022-08-18 00:43:26

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