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Conceptual design and comprehensive optimization analysis of a fusion- fission hybrid reactor water-cooled pressure tube blanket

机译:裂变混合反应堆水冷式压力管毯的概念设计和综合优化分析

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摘要

Fusion-fission hybrid reactor is believed to be a feasible implementation of fusion energy in a short time as it requires less advanced technology in fusion physics and engineering than pure fusion reactor. In this paper, based on the mature technology of pressurized water reactor (PWR) and existing fusion reactor blanket concepts, a new conceptual design scheme of water-cooled pressure tube blanket was proposed for hybrid reactor and both the material selections and the structure design were performed. In the blanket, a trapezoidal U-shaped first wall (FW) was adopted to decrease the gaps between blanket modules. Due to high heat flux from plasma and intense irradiation by high-energy neutrons, it's essential to conduct thermal-mechanical coupling analyses and optimizations of the FW to ensure reasonable temperature and stress distributions on it. In this work, CFX-Workbench coupling method was adopted to perform the simulation. The influences of different FW geometrical configurations and boundary conditions on the temperature and stress distributions were researched in detail to optimize the FW structure. Besides, the thermal and mechanical characteristics of the helium tanks, the cooling channels and the breeding zones were researched in this paper. The calculation results verified the reasonability of the conceptual design scheme preliminarily and could provide a meaningful reference for the further conceptual design, analysis and optimization of the hybrid reactor blanket.
机译:聚变裂变混合反应堆被认为是在短时间内实现聚变能的可行方法,因为与纯聚变反应堆相比,聚变裂变混合堆在聚变物理学和工程学上需要的先进技术较少。本文基于压水堆技术的成熟技术和现有的聚变反应堆毯概念,提出了一种新的混合反应堆水冷式压力管毯概念设计方案,并对其材料选择和结构设计进行了研究。执行。在毯子中,采用梯形U形第一壁(FW)来减小毯子模块之间的间隙。由于等离子体产生的高热通量和高能中子的强烈辐照,因此必须对FW进行热力耦合分析和优化,以确保其合理的温度和应力分布。在这项工作中,采用CFX-Workbench耦合方法进行仿真。详细研究了不同的固件结构和边界条件对温度和应力分布的影响,以优化固件结构。此外,还研究了氦气罐的热力学特性,冷却通道和繁殖区。计算结果初步验证了概念设计方案的合理性,可为进一步设计,分析和优化混合动力反应堆毯提供有意义的参考。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2018年第3期|8-19|共12页
  • 作者单位

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China;

    Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China;

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

    Fusion-fission hybrid reactor; Water-cooled pressure tube blanket; Conceptual design; First wall; Thermal-mechanical coupling;

    机译:裂变混合反应堆;水冷压力管毯;概念设计;第一壁;热力耦合;

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