THERMAL, HYDRAULIC, AND CORROSION ASPECTS OF PWR STEAM GENERATOR PROBLEMS.

被引：0
|
作者：
Green, Stanley J. [1 ]
机构：
[1] EPRI, Palo Alto, CA, USA, EPRI, Palo Alto, CA, USA
来源：
Heat Transfer Engineering | 1988年 / 9卷 / 01期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
163
引用
收藏
页码：19 / 68
相关论文
共 50 条
  • [21] ASSESSMENT OF PRIMARY WATER-STRESS CORROSION CRACKING OF PWR STEAM-GENERATOR TUBES
    SHAH, VN
    LOWENSTEIN, DB
    TURNER, APL
    WARD, SR
    GORMAN, JA
    MACDONALD, PE
    WEIDENHAMER, GH
    NUCLEAR ENGINEERING AND DESIGN, 1992, 134 (2-3) : 199 - 215
  • [22] PWR CORE THERMAL-HYDRAULIC RESPONSE DURING STEAM LINE BREAK ACCIDENT
    KERN, RC
    SIMONSON, SC
    NORIAN, PE
    SALAH, S
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 442 - 443
  • [23] Thermo-hydraulic transient behavior calculation of once-through steam generator of integrated PWR
    Xie, Heng
    Zhang, Jinling
    Jia, Dounan
    Su, Guanghui
    Yu, Zhenwan
    Qiu, Suizheng
    Hedongli Gongcheng/Nuclear Power Engineering, 1998, 19 (05): : 413 - 418
  • [24] Scaling analysis of the thermal hydraulic behavior in the secondary side of steam generator
    Wang, L. S.
    Yan, B. H.
    ANNALS OF NUCLEAR ENERGY, 2021, 164
  • [25] DEVELOPMENT OF THERMAL-HYDRAULIC COMPUTER CODE FOR STEAM-GENERATOR
    HIRAO, Y
    NAKAMORI, N
    UKAI, O
    KAWANISHI, K
    TSUGE, A
    UENO, T
    KUSAKABE, T
    JSME INTERNATIONAL JOURNAL SERIES B-FLUIDS AND THERMAL ENGINEERING, 1993, 36 (03) : 456 - 463
  • [26] Effects of power level on thermal-hydraulic characteristics of steam generator
    Cong, Tenglong
    Zhang, Rui
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROGRESS IN NUCLEAR ENERGY, 2015, 81 : 245 - 253
  • [27] Thermal hydraulic simulation of the steam generator under fast transient events
    Godino, Dario M.
    Corzo, Santiago F.
    Ramajo, Damian E.
    ANNALS OF NUCLEAR ENERGY, 2023, 180
  • [28] Thermal-hydraulic simulation of localized flow characteristics in a steam generator
    Ferng, YM
    Ma, YP
    Kang, JC
    NUCLEAR TECHNOLOGY, 2001, 136 (02) : 186 - 196
  • [29] THERMAL-HYDRAULIC STUDIES OF THE STEAM SEPARATION IN HORIZONTAL STEAM GENERATOR AT PGV TEST FACILITY
    Parfenov, Yuriy V.
    Melikhov, Oleg I.
    Melikhov, Vladimir I.
    Elkin, Ilya V.
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 3, 2009, : 265 - 267
  • [30] EVALUATION OF PWR STEAM GENERATOR TUBING ALLOYS.
    Berge, Ph.
    Donati, J.R.
    Nuclear Energy, 1978, 17 (04): : 291 - 299
12345