首页> 外文期刊>Nuclear Technology >SAFETY ANALYSIS OF BWR-HD: AN OPTIMIZED BOILING WATER REACTOR WITH HIGH POWER DENSITY
【24h】

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

机译:BWR-HD的安全性分析:一种高功率密度的优化沸腾水反应器

获取原文
获取原文并翻译 | 示例
       

摘要

An optimization search over all design parameters yields a boiling water reactor (BWR) with high power density (BWR-HD) at a power level of 5000 MW(thermal), equivalent to a 26% uprated Advanced BWR (ABWR), the latest version of operating BWR. This results in economic benefits, estimated to be -20% capital and operation and maintenance costs and similar total fuel cycle cost per unit electricity. A safety analysis of the BWR-HD was performed and compared with that of the ABWR. It covered a range of transients, involving a decrease in reactor coolant inventory or coolant system flow rate, changes in coolant temperature along with increase in reactor pressure, and a reactivity-initiated transient. The BWR-HD's different core flow velocity, feedwater flow rate, core inlet temperature, void coefficient of reactivity, pressure drop, core fuel loading, and volume of fluid in the core resulted in very different response to transients. In general, the 1.3-m-shortercore results in faster scram times and lower total positive reactivity insertions during the transients, which improves the BWR-HD's performance compared to that of the ABWR. The core remains covered and the pressure in the reactor pressure vessel never rises above the licensing limits during any of the simulated transients. The change in minimum critical power ratio for the BWR-HD was smaller than or equal to that of the reference ABWR in all of the six simulated transients. For the loss-of-coolant-inventory accidents and severe accidents, the BWR-HD qualitative performance was judged to be acceptable and could result in an improved response with the lower fuel and zirconium loading.
机译:通过对所有设计参数进行优化搜索,可以得到功率水平为5000 MW(热)的高功率密度(BWR-HD)沸水反应堆(BWR),相当于最新版本的先进BWR(ABWR)提高了26%操作BWR。这产生了经济效益,估计为-20%的资金以及运营和维护成本,以及每单位电力的类似燃料循环总成本。进行了BWR-HD的安全性分析,并与ABWR进行了安全性分析。它涵盖了一系列瞬变,包括反应堆冷却剂存量或冷却剂系统流量的减少,冷却剂温度的变化以及反应堆压力的增加以及反应性引发的瞬变。 BWR-HD不同的岩心流速,给水流速,岩心入口温度,空洞反应系数,压力降,岩心燃料负荷和岩心中的流体量导致对瞬态的响应截然不同。通常,1.3 m的更短内核可在瞬变期间缩短加扰时间并降低总的正反应性插入,与ABWR相比,可提高BWR-HD的性能。在任何模拟的瞬变过程中,堆芯仍保持覆盖状态,反应堆压力容器中的压力永远不会超过许可极限。在所有六个模拟瞬变中,BWR-HD的最小临界功率比的变化小于或等于参考ABWR的变化。对于冷却液库存不足事故和严重事故,BWR-HD的定性性能被认为是可以接受的,并且可以在较低的燃料和锆负荷下提高响应速度。

著录项

  • 来源
    《Nuclear Technology》 |2013年第3期|274-286|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; Advanced BWR design; nuclear safety analysis;

    机译:大功率沸水反应堆;先进的BWR设计;核安全分析;
  • 入库时间 2022-08-18 00:43:26

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号