ADS原理验证装置两种方案的热工水力分析

刘展, 杨燕华, 刘兴民, 沈峰

刘展, 杨燕华, 刘兴民, 沈峰. ADS原理验证装置两种方案的热工水力分析[J]. 原子能科学技术, 2010, 44(4): 423-428. DOI: 10.7538/yzk.2010.44.04.0423
引用本文: 刘展, 杨燕华, 刘兴民, 沈峰. ADS原理验证装置两种方案的热工水力分析[J]. 原子能科学技术, 2010, 44(4): 423-428. DOI: 10.7538/yzk.2010.44.04.0423
LIU Zhan, YANG Yan-hua, LIU Xing-min, SHEN Feng. Thermal-Hydraulic Research of Two Schemes on ADS Principle Verification Facility[J]. Atomic Energy Science and Technology, 2010, 44(4): 423-428. DOI: 10.7538/yzk.2010.44.04.0423
Citation: LIU Zhan, YANG Yan-hua, LIU Xing-min, SHEN Feng. Thermal-Hydraulic Research of Two Schemes on ADS Principle Verification Facility[J]. Atomic Energy Science and Technology, 2010, 44(4): 423-428. DOI: 10.7538/yzk.2010.44.04.0423

ADS原理验证装置两种方案的热工水力分析

Thermal-Hydraulic Research of Two Schemes on ADS Principle Verification Facility

  • 摘要: 加速器驱动的次临界系统(ADS)项目是“973项目”之一,旨在解决ADS的关键技术问题。其中,“原理验证装置的设计”课题可为ADS关键技术的解决和走向工程化奠定基础。文章就两种不同的堆芯方案陈述了ADS原理验证装置热工水力的计算,计算由初始稳态运行和瞬态及事故工况组成。为考察两种方案的自然循环能力,选择失流事故进行瞬态分析。对瞬态工况的严重性和两种方案的结果进行了比较,结果表明:事故工况下自然循环可足够带走堆芯余热,且方案1比方案2的安全裕度大。

     

    Abstract: Accelerator-driven sub-critical system (ADS) project is one of “973 Project”, which aims to solve ADS key issue. The design of principle verification facility could provide the platform of solving ADS key issue and engineering design. Based on two different core schemes, the paper presents the thermal-hydraulic theoretical analysis on ADS principle verification device. It consists of initial steady and transient accidental analysis. To find out the level of natural circulation, loss of flow was researched in transient analysis. In the end, the seriousness of transient cases and the result of two schemes were compared. The results show that in transient accident the natural circulation can remove core residual heat enough; and the first scheme is bigger than the second scheme in terms of safe margin.

     

  • [1] CHENG X, CAHALAN J E, FINCK P J. Safety analysis of an acceleratordriven test facility[J]. Nuclear Engineering and Design, 2004, 229: 289-306.
    [2] 刘天才,杨长江,刘兴民,等.中国先进研究堆安全设计[J]. 核动力工程, 2006, 27(5增刊):29-31.
    LIU Tiancai, YANG Changjiang, LIU Xingmin, et al. Safety design of China Advanced Research Reactor[J]. Nuclear Power Engineering, 2006, 27, (5S2): 29-31(in Chinese).
    [3] TIAN W X, QIU S Z, GUO Y, et al. Development of a thermal-hydraulic analysis code for CARR[J]. Annals Nuclear Energy,2005, 32 (3): 261-279.
    [4] 尤洪君,崔震华,程轶平.板状燃料元件热传导模型及其动态仿真[J]. 核科学与工程,2001,22(1):59-62.
    YOU Hongjun, CUI Zhenhua, CHENG Yiping. Thermal conduction model and its dynamic simulation of plate type fuel element[J]. Journal of Nuclear Science and Engineering, 2002, 22(1): 59-62(in Chinese).
    [5] 孙荣先. U3Si2-Al弥散型燃料元件[J]. 核动力工程,1990,11(2):69-73.
    SUN Rongxian. U3Si2-Al dispersion fuel element [J]. Nuclear Power Engineering, 1990, 11(2): 69-73(in Chinese).
    [6] 袁履正,柯国土,金华晋,等. 中国先进研究堆(CARR)的设计特点和创新技术[J]. 核动力工程,2006,27(5增刊):1-5.
    YUAN Lüzheng, KE Guotu, JIN Huajin, et al. Features and innovatives of China Advanced Research Reactor (CARR) design[J]. Nuclear Power Engineering, 2006, 27(5S2): 1-5(in Chinese).
计量
  • 文章访问数:  815
  • HTML全文浏览量:  0
  • PDF下载量:  1024
  • 被引次数: 0
出版历程
  • 收稿日期:  1899-12-31
  • 修回日期:  1899-12-31
  • 刊出日期:  2010-04-19

目录

    /

    返回文章
    返回