Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes

被引：1
|
作者：
Kozmenkov, Y. [1 ]
Rohde, U. [1 ]
Baranaev, Y. [2 ]
Glebov, A. [2 ]
机构：
[1] HZDR, D-01328 Dresden, Germany
[2] Russian Federat Inst Phys & Power Engn, State Sci Ctr, Obninsk 249020, Russia
来源：
KERNTECHNIK | 2012年 / 77卷 / 04期
关键词：
D O I：
10.3139/124.110250
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：
RUTA-70 model for simulations with the internally coupled codes DYN3D/ATHLET and DYN3D/RELAP5 was developed. A 3-D power distribution in the core is calculated by DYN3D with thermal-hydraulic feedback from the system codes. A steady-state corresponding to the full reactor power and at accident scenario initiated by failure of all primary codes pumps were simulated with the DYN3D/ATHLET and LYN3D/RELAP5 coupled code systems to verify these codes. The compared coupled codes give close predictions for the initial and final states of the simulated accident but not for the transition between them. The observed deviations are explained by differences in the subcooled boiling models of the employed versions of ATHLET and RELAP5. Nevertheless., both simulations confirm a high level of the reactor inherent safety. The allowed safety margins were not reached.
引用
收藏
页码：249 / 257
页数：9
相关论文
共 50 条
  • [1] 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
  • [2] 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
  • [3] 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
  • [4] The reactor dynamics code DYN3D
    Kliem, S.
    Bilodid, Y.
    Fridman, E.
    Baier, S.
    Grahn, A.
    Gommlich, A.
    Nikitin, E.
    Rohde, U.
    [J]. KERNTECHNIK, 2016, 81 (02) : 170 - 172
  • [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] Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculations
    Kliem, S.
    Kozmenkov, Y.
    Hoehne, T.
    Rohde, U.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2006, 48 (08) : 830 - 848
  • [7] 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
  • [8] Application of ATHLET/DYN3D coupled codes system for fast liquid metal cooled reactor steady state simulation
    Ivanov, V.
    Samokhin, A.
    Danicheva, I.
    Khrennikov, N.
    Bouscuet, J.
    Velkov, K.
    Pasichnyk, I.
    [J]. INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS, AND POSTGRADUATES ON NUCLEAR REACTOR PHYSICS 2016 (ICNRP-2016), 2017, 781
  • [9] 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
  • [10] 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
12345