AN OVERVIEW OF IN-VESSEL RELEASE AND CHEMISTRY MODELING IN SEVERE ACCIDENT ANALYSIS CODES

被引:0
|
作者
GRIMLEY, AJ [1 ]
机构
[1] SANDIA NATL LABS, DIV 6425, ALBUQUERQUE, NM 87185 USA
关键词
D O I
暂无
中图分类号
O6 [化学];
学科分类号
0703 ;
摘要
引用
收藏
页码:126 / NUCL
相关论文
共 50 条
  • [41] Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout
    Guo, Zehua
    Dailey, Ryan
    Feng, Tangtao
    Zhou, Yukun
    Sun, Zhongning
    Corradini, Michael L.
    Wang, Jun
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2021, 213
  • [42] SAFETY EVALUATION OF PROTOTYPE FAST-BREEDER REACTOR - Analysis of ULOF Accident to demonstrate In-Vessel Retention y
    Suzuki, Tohru
    Tobita, Yoshiharu
    Kawada, Kenichi
    Tagami, Hirotaka
    Sogabe, Joji
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 6, 2014,
  • [43] Thermal hydraulic analysis of in-vessel loss of coolant accident for the EAST lower divertor primary heat transfer system
    Zhou, Jinxuan
    Hu, Jiansheng
    Guo, Bin
    Yang, Lei
    Li, Weibao
    FUSION ENGINEERING AND DESIGN, 2024, 206
  • [44] Uncertainty analysis on early health effects modeling in accident consequence codes
    Kraan, B
    Cooke, R
    Goossens, L
    PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT (PSAM 4), VOLS 1-4, 1998, : 1077 - 1082
  • [45] Analysis of prestressed concrete containment vessel (PCCV) under severe accident loading
    Noh, Sang Hoon
    Moon, Il Hwan
    Lee, Jong Bo
    Kim, Jong Hak
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (01) : 77 - 86
  • [46] Probability analysis for external reactor vessel cooling effectiveness under severe accident
    Cao, Ke-Mei
    Xu, Yi-Quan
    Shi, Guo-Bao
    Cai, Jian-Ping
    Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (01): : 1 - 4
  • [47] The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system
    Salehi, Mohsen
    Shayesteh, Mohsen
    ANNALS OF NUCLEAR ENERGY, 2017, 107 : 1 - 16
  • [48] Comprehensive integral simulation of first 3 weeks of severe accident at Fukushima Daiichi Unit 1. Part II - Simulation of the in-vessel and ex-vessel phases
    Dolganov, Kirill S.
    Kiselev, Arkady E.
    NUCLEAR ENGINEERING AND DESIGN, 2024, 428
  • [49] MATERIALS CHEMISTRY AND TRANSPORT MODELING FOR SEVERE ACCIDENT ANALYSES IN LIGHT-WATER REACTORS .2. GAP PROCESSES AND HEAT RELEASE
    OLANDER, DR
    NUCLEAR ENGINEERING AND DESIGN, 1994, 148 (2-3) : 273 - 292
  • [50] Simplified modeling of a PWR reactor pressure vessel lower head failure in the case of a severe accident
    Koundy, V
    Durin, A
    Nicolas, L
    Combescure, A
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (08) : 835 - 843