EXPERIMENTAL EVALUATION OF POST-LOCA STEAM RELIEF

被引:0
|
作者
BURCHILL, WE [1 ]
LOWE, PA [1 ]
机构
[1] COMBUSTION ENGN INC, WINDSOR, CT 06095 USA
来源
关键词
D O I
暂无
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
引用
收藏
页码:830 / +
相关论文
共 50 条
  • [21] Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
    Wang, Cheng-Der
    KERNTECHNIK, 2023, 88 (02) : 221 - 230
  • [22] Assessment of post-LOCA long term cooling considering the in-vessel downstream effect
    Amin, Shah Asad Ullah
    Bang, Young Seok
    Lee, Joo-Seok
    ANNALS OF NUCLEAR ENERGY, 2017, 110 : 63 - 72
  • [23] The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations
    Kitano, Koji
    Ozawa, Masaaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2024, 61 (04) : 498 - 508
  • [24] JCO criticality accident as POST-LOCA: Poor structure induced loss of organizational control accident
    Furuhama, Y
    PSAM 5: PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT, VOLS 1-4, 2000, (34): : 2165 - 2170
  • [25] Multi-pin modelling of PWR fuel pin ballooning during post-LOCA reflood
    Ammirabile, L.
    Walker, S. P.
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (06) : 1448 - 1458
  • [26] Prediction of Leak Flow Rate Using Fuzzy Neural Networks in Severe Post-LOCA Circumstances
    Kim, Dong Yeong
    Yoo, Kwae Hwan
    Kim, Ju Hyun
    Na, Man Gyun
    Hur, Seop
    Kim, Chang-Hwoi
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2014, 61 (06) : 3644 - 3652
  • [27] POST-LOCA DOSE-RATES ON RHR SYSTEM PIPING BASED ON A PARTICLE SETTING MODEL
    LIBBY, V
    BROWN, GJ
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 500 - 502
  • [28] The contribution of non-wetting droplets to direct cooling of the fuel during PWR post-LOCA reflood
    Chatzikyriakou, D.
    Walker, S. P.
    Hewitt, G. F.
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) : 3108 - 3114
  • [29] An Evaluation Of Post-LOCA Debris On Multi-Stage Safety-Related Pumps In PWR ECCS In Support Of Generic Safety Issue 191 Closure
    Ezekoye, L. Ike
    Hundal, Rolv
    Pyle, Paul V.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7, 2009, : 323 - 328
  • [30] Analysis of post-LOCA long-term core safety characteristics for the Small Modular Reactor ACP100
    Deng, Jian
    Dang, Gaojian
    Ding, Shuhua
    Qiu, Zhifang
    ANNALS OF NUCLEAR ENERGY, 2020, 142