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Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes

机译:采用ATTICA3D和THERMIX编码的卵石床模块化高温气冷堆的热工水力分析

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摘要

Along with the further ongoing design procedures of a large demonstration power plant of Chinese 200 MWe high temperature gas-cooled reactor pebble-bed module (HTR-PM), three-dimensional (3-D) analysis is necessary for studying the reactor characteristics under some special unsymmetrical conditions. Compared with the well established two-dimensional thermal-hydraulics code THERMIX, a new three-dimensional system analysis code ATTICA3D (Advanced Thermal hydraulics Tool for In-vessel & Core Analysis in 3D), developed by IKE of University of Stuttgart on the basis of TH3D, is used to perform the steady state calculation and transient analysis of a depressurized loss of coolant accident (DLOCA) for the HTR-PM. After a brief introduction of the reactor primary circuit, the above two codes, including correlative typical parameters and relevant formulae are described in detail. Then an ATTICA3D model, which keeps consistent with the THERMIX model as much as possible, is constructed according to the preliminary design of the HTR-PM. Based on the cylindrically symmetrical power distribution, the comparisons of the two-dimensional calculations between ATTICA3D and THERMIX indicate, that the main results including pressure drop and temperature distribution show good agreement. Furthermore, considering one set of small absorber spheres (SAS) dropping into the side reflectors resulting in an asymmetric distribution of the nuclear power, a three-dimensional calculation for the steady state is implemented to basically show the good 3-D simulation capabilities of ATTICA3D, which will be helpful to the next refined design stage for the HTR-PM project. It should be pointed out that the current 3-D simulation results illustrated in this paper are still preliminary, and more research work, e.g., comparison with experimental data or with some commercial CFD codes, needs to be carried out in order to further validate the ATTICA3D code and study the special 3-D characteristics of the HTR-PM in the future.
机译:随着中国200 MWe高温气冷堆卵石床模块(HTR-PM)的大型示范电厂的进一步设计程序的进行,必须进行三维(3-D)分析来研究在以下条件下的反应堆特性一些特殊的不对称条件。与完善的二维热工液压代码THERMIX相比,斯图加特大学IKE在斯图加特大学的基础上开发了新的三维系统分析代码ATTICA3D(用于3D容器和岩心分析的高级热工液压工具)。 TH3D用于对HTR-PM进行降压的冷却液损失事故(DLOCA)的稳态计算和瞬态分析。在简要介绍电抗器一次回路后,详细描述了上述两个代码,包括相关的典型参数和相关的公式。然后根据HTR-PM的初步设计,构建了一个与THERMIX模型尽可能保持一致的ATTICA3D模型。基于圆柱对称的功率分布,ATTICA3D和THERMIX的二维计算比较表明,包括压降和温度分布在内的主要结果吻合良好。此外,考虑到一组小吸收器球体(SAS)掉入侧反射器中导致核电的不对称分布,因此对稳态进行了三维计算,以基本显示ATTICA3D的良好3D模拟能力,这将有助于HTR-PM项目的下一个改进设计阶段。应当指出的是,本文中说明的当前3-D仿真结果仍是初步的,需要进行更多的研究工作,例如与实验数据或某些商业CFD代码进行比较,以进一步验证ATTICA3D编码并研究HTR-PM的特殊3-D特性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第5期|p.286-297|共12页
  • 作者单位

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

    Institute of Nuclear Technology and Energy System, University of Stuttgart, Germany;

    Institute of Nuclear Technology and Energy System, University of Stuttgart, Germany;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

  • 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
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