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Thermal hydraulic feasibility analysis of the IBED PHTS for ITER

机译:用于ITER的IBED PHTS的热力水力可行性分析

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摘要

One of the main challenges of the ITER fusion reactor is to effectively remove large amount of heat deposited to the surface of the plasma facing components. The tokamak cooling water system (TCWS) will accomplish the objective of removing about 1 GW of peak heat load from in-vessel components while maintaining pressures and temperatures of the coolant within acceptable and safe limits during different operational scenarios. A study of feasibility has been launched for the IBED PHTS (Integrated Blanket, Edge localized mode coils (ELMs) and Divertor Primary Heat Transfer System; it consists of five independent cooling trains (four operational and one in stand-by), one steam pressurizer, supply and return headers, ring manifolds and connections to the all in-vessel components (i.e. First Wall Blanket, Divertor, ELM, Diagnostics and other Ports clients). The dynamic behaviour of the IBED PHTS has been investigated by means of RELAP5~® code to simulate the response of the system during plasma pulse and baking operations. Due to the plasma heat deposition on the surfaces of the in-vessel components and subsequent increase in hot leg temperature, a large amount of water volume is transferred from the hot legs of the circuit to the surge-line of the pressurizer during each burn cycle. This causes rapid increase of pressure and temperature of the system and the following actions are proposed to counteract these variations: spray injection in the upper dome of the pressurizer from the Chemical and Volume Control System (CVCS) to reduce the pressure and active control of flow rates through heat exchangers and their bypass loops to regulate the heat transfer from the primary system to the environment via secondary and tertiary loops. This paper focuses on the prediction of the thermal hydraulic behaviour of the IBED PHTS during plasma pulses and baking scenarios, describing the various activity of the analysis, the geometrical assessment of the circuit and the modelling with RELAP5~® code. The results have been compared with design and operational requirement. Possible strategies to enhance the system performances have been formulated.
机译:ITER聚变反应堆的主要挑战之一是有效去除沉积在面对等离子体的组件表面的大量热量。托卡马克冷却水系统(TCWS)的目标是消除船上部件的约1 GW峰值热负荷,同时在不同的操作场景下将冷却剂的压力和温度保持在可接受的安全范围内。已经开始对IBED PHTS(集成式毯子,边缘局部模式线圈(ELM)和分流器一次换热系统)进行可行性研究;它由5个独立的冷却机组(4个运行中的机组和1个备用机组),1个蒸汽加压器组成,供应集管和返回集管,环形歧管以及与所有容器内组件(即第一壁毯,分流器,ELM,诊断和其他端口客户端)的连接已通过RELAP5〜®研究了IBED PHTS的动态行为该代码可模拟系统在等离子脉冲和烘烤操作过程中的响应由于等离子体在容器内组件表面上的热量沉积以及随后热腿温度的升高,大量的水从热腿转移在每个燃烧循环中将电路连接至增压器的喘振线,这会导致系统的压力和温度快速升高,因此建议采取以下措施来抵消这些压力变化:从化学和体积控制系统(CVCS)向增压器的上半部喷雾,以降低压力并主动控制通过热交换器及其旁通回路的流量,从而调节从主系统到环境的热传递通过第二和第三循环。本文着重于预测IBED PHTS在等离子脉冲和烘烤情况下的热水力行为,描述分析的各种活动,电路的几何评估以及使用RELAP5〜®代码进行建模。将结果与设计和操作要求进行了比较。已经制定了增强系统性能的可能策略。

著录项

  • 来源
    《Fusion Engineering and Design》 |2013年第10期|1709-1713|共5页
  • 作者单位

    Dipartimento di Ingegneria Meccanica, Nucleare e delta Produzione, Pisa University, Via Diotisalvi 2,56126 Pisa, Italy;

    ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;

    ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;

    ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;

    ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;

    Dipartimento di Ingegneria Meccanica, Nucleare e delta Produzione, Pisa University, Via Diotisalvi 2,56126 Pisa, Italy;

  • 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

    ITER; IBED; RELAP5~*;

    机译:ITER;IBED;RELAP5〜*;

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