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Concept of a high temperature integrated multi-modular thermal reactor

机译:高温集成多模热反应堆的概念

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摘要

The high temperature integrated multi-modular thermal reactor is a first-of-a-kind small modular reactor that uses an enhanced conductivity BeO-UO_2 fuel with supercritical CO-2 coolant to drive turbo-machinery in a direct Brayton cycle. The core consists of several self-contained pressurized modules, each containing fuel elements in pressurized channels surrounded by a graphite moderator, and Brayton cycle turbo-machinery. Each module is subcritical by itself, and when several modules are brought into proximity of one another, a single critical core is formed. The multi-modular approach and use of BeO-UO-2 fuel with graphite moderator and supercritical CO-2 coolant leads to an inherently safe system capable of high efficiency operation. The pressure channel design and multi-modular approach eliminates engineering challenges associated with large pressure vessels, and the subcriticality of the modules ensures inherent safety during construction, transportation, and after decommissioning. A feasible configuration consisting of seven modules operating for 14.7 years at 10MWth power using 5% BeO and 5% 235U enriched fuel is presented in this paper. The results of the conceptual analysis include flux and power distributions as well as potential power shaping and reactivity coefficients were analyzed.
机译:高温集成多模块热反应堆是首创的小型模块化反应堆,它使用电导率更高的BeO-UO_2燃料和超临界CO-2冷却剂,直接在布雷顿循环中驱动涡轮机械。堆芯由几个独立的加压模块组成,每个模块都在加压通道中包含燃料元件,该通道中的燃料被石墨减速器和布雷顿循环涡轮机械包围。每个模块本身都是亚临界的,当几个模块相互靠近时,就会形成一个关键的核心。 BeO-UO-2燃料的多模块方法以及石墨缓和剂和超临界CO-2冷却剂的使用导致了本质上安全的系统,能够高效运行。压力通道设计和多模块方法消除了与大型压力容器相关的工程挑战,模块的亚临界特性确保了在施工,运输和退役后的固有安全性。本文提出了一个可行的配置,该配置由七个模块组成,这些模块使用5%BeO和5%235U浓缩燃料以10MWth的功率运行14.7年。概念分析的结果包括通量和功率分布以及潜在的功率整形和反应性系数。

著录项

  • 来源
    《Annals of nuclear energy》 |2013年第5期|312-321|共10页
  • 作者

    Vishal Patel; Pavel Tsvetkov;

  • 作者单位

    Department of Nuclear Engineering, Texas A&M University, 337 Zachry Engineering Center, 3X33 TAMU College Station, TX 77843-3133, United States;

    Department of Nuclear Engineering, Texas A&M University, 337 Zachry Engineering Center, 3X33 TAMU College Station, TX 77843-3133, United States;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    high temperature; reactor design; SMR; beo-UO_2 fuel; supercritical CO-2;

    机译:高温;反应堆设计;SMR;beo-UO_2燃料;超临界CO-2;

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