首页> 外文会议>ICONE18;International conference on nuclear engineering >Thermal Aspects of Using Uranium Mononitride Fuel in a Supercritical Water-Cooled Reactor at Maximum Heat Flux Conditions
【24h】

Thermal Aspects of Using Uranium Mononitride Fuel in a Supercritical Water-Cooled Reactor at Maximum Heat Flux Conditions

机译:在最大热通量条件下在超临界水冷反应堆中使用单氮化铀燃料的热学方面

获取原文

摘要

Generation IV nuclear reactor technology is increasing in popularity worldwide. One of the six Generation-IV-reactor types are Supercritical Water-cooled Reactors (SCWRs). The main objective of SCWRs is to increase substantially thermal efficiency of Nuclear Power Plants (NPPs) and thus, to reduce electricity costs. This reactor type is developed from concepts of both Light Water Reactors (LWRs) and supercritical fossil-fired steam generators. The SCWR is similar to a LWR, but operates at a higher pressure and temperature.The coolant used in a SCWR is light water, which has supercritical pressures and temperatures during operation. Typical light water operating parameters for SCWRs are a pressure of 25 MPa, an inlet temperature of 280 - 350°C, and an outlet temperature up to 625°C. Currently, NPPs have thermal efficiency about of 30 - 35%, whereas SCW NPPs will operate with thermal efficiencies of 45 - 50%. Furthermore, since SCWRs have significantly higher water parameters than current water-cooled reactors, they are able to support co-generation of hydrogen.Studies conducted on fuel-channel options for SCWRs have shown that using uranium dioxide (UO_2) as a fuel at supercritical-water conditions might be questionable. The industry accepted limit for the fuel centerline temperature is 1850°C and using UO_2 would exceed this limit at certain conditions. Because of this problem, there have been other fuel options considered with a higher thermal conductivity.A generic 43-element bundle for an SCWR, using uranium mononitride (UN) as the fuel, is discussed in this paper. The material for the sheath is Inconel-600, because it has a high resistance to corrosion and can adhere to the maximum sheath-temperature design limit of 850°C. For the purpose of this paper, the bundle will be analyzed at its maximum heat flux. This will verify if the fuel centerline temperature does not exceed 1850°C and that the sheath temperature remains below the limit of 850°C.
机译:第四代核反应堆技术在世界范围内日益普及。第四代IV反应器类型之一是超临界水冷反应堆(SCWR)。 SCWR的主要目标是显着提高核电厂(NPP)的热效率,从而降低电力成本。这种反应堆类型是根据轻水堆(LWR)和超临界化石燃料蒸汽发生器的概念开发的。 SCWR与LWR类似,但在更高的压力和温度下运行。 SCWR中使用的冷却剂是轻水,在运行期间具有超临界压力和温度。 SCWR的典型轻水操作参数是25 MPa的压力,280-350°C的入口温度和高达625°C的出口温度。当前,核电厂的热效率约为30-35%,而SCW核电厂的热效率为45-50%。此外,由于超临界水冷堆比目前的水冷反应堆具有更高的水参数,因此它们能够支持氢的联产。对超临界水冷堆的燃料通道选项进行的研究表明,在超临界状态下使用二氧化铀(UO_2)作为燃料-水的状况可能令人怀疑。业界公认的燃料中心线温度极限为1850°C,在某些情况下使用UO_2会超过该极限。由于这个问题,已经考虑了其他具有较高导热率的燃料选择。 本文讨论了使用单氮化铀(UN)作为燃料的SCWR的通用43元素束。护套的材料为Inconel-600,因为它具有很高的耐腐蚀性,并且可以遵守850°C的最高护套温度设计极限。出于本文的目的,将以束的最大热通量对其进行分析。这将验证燃料中心线温度是否不超过1850°C,并且护套温度是否低于850°C的极限。

著录项

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