Main steam line break analysis of a NPP with VVER by means of this coupled code DYN3D/ATHLET

被引:0
|
作者
Kliem, S [1 ]
Grundmann, U [1 ]
Rohde, U [1 ]
机构
[1] Rossendorf Inc, Forschungszentrum Rossendorf EV, Inst Sicherheitsforsch, D-01314 Dresden, Germany
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:15 / 19
页数:3
相关论文
共 34 条
  • [1] Main steam line break analysis of a NPP with VVER by means of the coupled code DYN3D/ATHLET
    Kliem, S
    Grundmann, U
    Rohde, U
    [J]. ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 15 - 19
  • [2] Analyses of the OECD Main Steam Line Break Benchmark with the DYN3D and ATHLET codes
    Grundmann, U
    Kliem, S
    [J]. NUCLEAR TECHNOLOGY, 2003, 142 (02) : 146 - 153
  • [3] Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
    Hadek, J.
    Meca, R.
    [J]. KERNTECHNIK, 2018, 83 (04) : 376 - 388
  • [4] Analysis of the OECD MSLB benchmark using the coupled code DYN3D/ATHLET
    Kliem, S
    Grundmann, U
    Rohde, U
    [J]. JAHRESTAGUNG KERNTECHNIK 2000 - ANNUAL MEETING ON NUCLEAR TECHNOLOGY 2000, 2000, : 7 - 10
  • [5] ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
    Kliem, S.
    Mittag, S.
    Rohde, U.
    Weiss, F. -P.
    [J]. ANNALS OF NUCLEAR ENERGY, 2009, 36 (08) : 1230 - 1234
  • [6] Calculation of the VVER-1000 coolant transient benchmark using the coupled code systems DYN3D/RELAP5 and DYN3D/ATHLET
    Kozmenkov, Y.
    Kliem, S.
    Grundmann, U.
    Rohde, U.
    Weiss, F.-P.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (15-17) : 1938 - 1951
  • [7] Validation and verification of the coupled neutron kinetic/thermal hydraulic system code DYN3D/ATHLET
    Kozmenkov, Y.
    Kliem, S.
    Rohde, U.
    [J]. ANNALS OF NUCLEAR ENERGY, 2015, 84 : 153 - 165
  • [8] Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the codes DYN3D and ATHLET/DYN3D
    Grundmann, U
    Kliem, S
    Rohde, U
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2004, 148 (02) : 226 - 234
  • [9] Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the coupled code system ATHLET-QUABOX/CUBBOX
    Langenbuch, S
    Schmidt, KD
    Velkov, K
    [J]. NUCLEAR TECHNOLOGY, 2003, 142 (02) : 124 - 136
  • [10] Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
    Kozmenkov, Y.
    Rohde, U.
    Baranaev, Y.
    Glebov, A.
    [J]. KERNTECHNIK, 2012, 77 (04) : 249 - 257