The theoretical and computational bases for the GASFLOW-II nuclear reactor safety containment code

被引:0
|
作者
Travis, JR [1 ]
Necker, G [1 ]
Royl, P [1 ]
机构
[1] Forschungszentrum Karlsruhe GMBH, Inst Reaktorsicherheit, D-76344 Karlsruhe, Germany
关键词
CFD; nuclear reactor safety; hydrogen; containment analysis; recombiner; igniter; combustion;
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
GASFLOW-II is a finite-volume computer code that solves the time-dependent compressible Navier-Stokes equations for multiple gas species in a dispersed liquid water two-phase medium, The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting gases to simulate diffusion or propagating flames in complex geometries of nuclear containments. GASFLOW-II is therefore able to predict gaseous distributions and thermal and pressure loads on containment structures and safety related equipment in the event combustion occurs. Current developments of GASFLOW-II are focused on hydrogen distribution, mitigation measures including carbon dioxide inerting, and possible combustion events in nuclear reactor containments. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. Condensation, vaporization, and heat transfer to walls, floors, ceilings, internal structures, and within the fluid are calculated to model the appropriate mass and energy sinks.
引用
收藏
页码:301 / 306
页数:6
相关论文
共 35 条
  • [21] Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III - Theoretical modeling and basic verification
    Morita, K
    Matsumoto, T
    Akasaka, R
    Fukuda, K
    Suzuki, T
    Tobita, Y
    Yamano, H
    Kondo, S
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2003, 220 (03) : 224 - 239
  • [22] Theory and implementation of nuclear safety system codes - Part II: System code closure relations, validation, and limitations
    Roth, Glenn A.
    Aydogan, Fatih
    [J]. PROGRESS IN NUCLEAR ENERGY, 2014, 76 : 55 - 72
  • [23] Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries
    Uddin, M. N.
    Sarker, M. M.
    Khan, M. J. H.
    Islam, S. M. A.
    [J]. ANNALS OF NUCLEAR ENERGY, 2010, 37 (03) : 302 - 309
  • [24] COMPREHENSIVE SAFETY ANALYSIS CODE SYSTEM FOR NUCLEAR-FUSION REACTORS .1. MODEL AND ANALYSES OF OVERPOWER EVENTS FOR THE INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR
    HONDA, T
    UDA, T
    MAKI, K
    OKAZAKI, T
    SEKI, Y
    AOKI, I
    [J]. FUSION TECHNOLOGY, 1994, 25 (04): : 451 - 468
  • [25] Investigations on water condensation in the main steam pipe of a pressurized water reactor nuclear power station: Part II- Theoretical studies
    He, Kun
    Li, Jun
    Yan, Xin
    Feng, Zhenping
    Fan, Yizhi
    Shang, Xianyou
    [J]. PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART A-JOURNAL OF POWER AND ENERGY, 2014, 228 (04) : 391 - 401
  • [26] COMPREHENSIVE SAFETY ANALYSIS CODE SYSTEM FOR NUCLEAR-FUSION REACTORS .2. THERMAL ANALYSES DURING PLASMA DISRUPTIONS FOR INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR
    HONDA, T
    MAKI, K
    OKAZAKI, T
    UDA, T
    SEKI, Y
    AOKI, I
    KUNUGI, T
    [J]. FUSION TECHNOLOGY, 1994, 26 (04): : 1288 - 1295
  • [27] Computer codes in the safety analysis for nuclear power plants. Computational capabilities of thermal-hydraulic tools, using the example of the RELAP5 code
    Skrzypek, Eleonora
    Skrzypek, Maciej
    [J]. JOURNAL OF POWER TECHNOLOGIES, 2014, 94 (05): : 41 - 50
  • [28] Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neutronic and thermal-hydraulics coupling
    Rahnama, Z.
    Ansarifar, G. R.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2021, 138
  • [29] Determination and Fabrication of New Shield Super Alloys Materials for Nuclear Reactor Safety by Experiments and Cern-Fluka Monte Carlo Simulation Code, Geant4 and WinXCom
    Aygun, Bunyamin
    Korkut, Turgay
    Karabulut, Abdulhalik
    [J]. INTERNATIONAL PHYSICS CONFERENCE AT THE ANATOLIAN PEAK (IPCAP2016), 2016, 707
  • [30] Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code
    Darif, Abdelaziz
    Chetaine, Abdelouahed
    Mghar, Mohammed
    Kabach, Ouadie
    [J]. TURKISH JOURNAL OF PHYSICS, 2018, 42 (01): : 41 - 46