The optimum design and arrangement of a steam generator in an integral pressurized water reactor

被引:0
|
作者
Wei, Xinyu [1 ]
Dai, Chunhui [2 ]
Wang, Pengfei [1 ]
Zhao, Fuyu [1 ]
机构
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China
[2] Wuhan Second Ship Des & Rec Inst, Lab Steam Power Syst, Wuhan 430064, Hubei, Peoples R China
基金
中国博士后科学基金; 中国国家自然科学基金;
关键词
Double-tube once-through steam generator (DOTSG); Pitch; Arrangement; Two-level optimization method; SAFETY FEATURES; OPTIMIZATION; FLOW;
D O I
10.1016/j.ijheatmasstransfer.2015.11.070
中图分类号
O414.1 [热力学];
学科分类号
摘要
This paper presents a double-tube once-through steam generator (DOTSG), whose tube unit includes an outer straight tube and an inner helical tube, in an integral pressurized water reactor (IPWR). To obtain the optimum structure of the inner helical tube and the arrangement of DOTSGs in the reactor pressure vessel, a two-level optimization method is used, aiming at the lower pumping power needed, and a smaller reactor pressure vessel volume is used. The pitch of inner helical tubes and the central distance of outer tubes are considered design parameters when minimizing the pumping power with the genetic algorithm in the bottom level, while the number of tube units in a single DOTSG and the number of DOTSGs in the reactor pressure vessel (RPV) are optimized to obtain the minimum volume of the IPWR, which is conducted in the top level. The optimum pitch of the helical tube varies in the sub cooled region, boiling region and superheated region. The results show that the smaller pitch brings a shorter tube length and a higher pressure drop, and the effects are strong in the sub-cooled region and the superheated region but weak in the boiling region. In this way, the optimal structure of the inner helical tube is a small pitch in the single-phase region and a large pitch in the boiling region. According to the bottom level results, the optimum arrangement of DOTSGs in the pressure vessel is determined. (C) 2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码:211 / 221
页数:11
相关论文
共 50 条
  • [1] The optimum design of power distribution for pressurized water reactor
    Dai, Chunhui
    Wei, Xinyu
    Tai, Yun
    Zhao, Fuyu
    ANNALS OF NUCLEAR ENERGY, 2012, 50 : 126 - 132
  • [2] Characteristics of steam generator tube deposits in an operating pressurized water reactor
    Jeon, Soon-Hyeok
    Hong, Seokmin
    Kwon, Hyuk-Chul
    Hur, Do Haeng
    JOURNAL OF NUCLEAR MATERIALS, 2018, 507 : 371 - 380
  • [3] Optimized adaptive fuzzy controller of the water level of a pressurized water reactor steam generator
    Marseguerra, M.
    Zio, E.
    Cadini, F.
    NUCLEAR SCIENCE AND ENGINEERING, 2007, 155 (03) : 386 - 394
  • [4] TRENDS IN DESIGN OF PRESSURIZED WATER REACTOR STEAM-GENERATORS
    KRIZEK, V
    KERNENERGIE, 1975, 18 (08): : 240 - 248
  • [5] Fault Diagnosis of Helical Coil Steam Generator Systems of an Integral Pressurized Water Reactor Using Optimal Sensor Selection
    Li, Fan
    Upadhyaya, Belle R.
    Perillo, Sergio R. P.
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2012, 59 (02) : 403 - 410
  • [6] IODINE PARTITIONING IN PRESSURIZED WATER-REACTOR STEAM-GENERATOR ACCIDENTS
    BEAHM, EC
    DAISH, SR
    SHOCKLEY, WE
    HOPENFELD, J
    NUCLEAR TECHNOLOGY, 1990, 90 (01) : 16 - 22
  • [7] MATERIALS REQUIREMENTS FOR PRESSURIZED WATER-REACTOR STEAM-GENERATOR TUBING
    BERGE, P
    DONATI, JR
    NUCLEAR TECHNOLOGY, 1981, 55 (01) : 88 - 104
  • [8] Pitting corrosion and its countermeasures for pressurized water reactor steam generator tubes
    Hur, D. H.
    Choi, M. S.
    Lee, D. H.
    Song, M. H.
    Han, J. H.
    CORROSION, 2006, 62 (10) : 905 - 910
  • [9] Research on Key Technology of Thermal Hydraulic Experiment of Pressurized Water Reactor Steam Generator
    Liao B.
    Wang Y.
    Wang X.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (11): : 2385 - 2394
  • [10] A fuzzy decision tree method for fault classification in the steam generator of a pressurized water reactor
    Zio, Enrico
    Baraldi, Piero
    Popescu, Irina Crenguta
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (08) : 1159 - 1169