An integrated RELAP5-3D and multiphase CFD code system utilizing a semi-implicit coupling technique

被引:32
|
作者
Aumiller, DL
Tomlinson, ET
Weaver, WL
机构
[1] Bettis Atom Power Lab, W Mifflin, PA 15122 USA
[2] Idaho Natl Engn & Environm Lab, Idaho Falls, ID 83415 USA
关键词
Algorithms - Computer software - Heat transfer - Loss of coolant accidents - Nuclear engineering;
D O I
10.1016/S0029-5493(01)00522-2
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
An integrated code system consisting Of RELAP5-3D and a multiphase Computational Fluid Dynamics (CFD) program has been created through the use of a generic semi-implicit coupling algorithm. Unlike previous CFD coupling work, this coupling scheme is numerically stable provided the material Courant limit is not violated in RELAP5-3D or at the coupling locations. The basis for the coupling scheme and details regarding the unique features associated with the application of this technique to a four-field CFD program are presented. Finally, the results of a verification problem are presented. The coupled code system is shown to yield accurate and numerically stable results. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:77 / 87
页数:11
相关论文
共 50 条
  • [21] Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator
    Wysocki, Aaron J. J.
    Salko, Robert K. K.
    Arshavsky, Igor
    NUCLEAR TECHNOLOGY, 2023, 209 (10) : 1466 - 1484
  • [22] Experimental and RELAP5-3D results on IELLLO (Integrated European Lead Lithium LOop) operation
    Venturini, A.
    Utili, M.
    Gabriele, A.
    Ricapito, I.
    Malavasi, A.
    Forgione, N.
    FUSION ENGINEERING AND DESIGN, 2017, 123 : 143 - 147
  • [23] Modeling of an air cooler with finned heat transfer tube banks using the RELAP5-3D code
    Mochizuki, Hiroyasu
    NUCLEAR ENGINEERING AND DESIGN, 2020, 370
  • [24] REACTOR CAVITY COOLING SYSTEM FACILITY SHAKEDOWN AND RELAP5-3D MODEL VALIDATION
    Vaghetto, R.
    Lee, Saya
    Hassan, Y. A.
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 3, 2012, : 775 - 782
  • [25] Thermal-hydraulic system study of a high pressure, high temperature helium loop using RELAP5-3D code
    Jin, Xue Zhou
    Ghidersa, Bradut-Eugen
    NUCLEAR ENGINEERING AND DESIGN, 2012, 249 : 57 - 62
  • [26] BEPU analysis of a passive decay heat removal system with RELAP5/ MOD3.3 and RELAP5-3D
    Alcaro, Fabio
    Bersano, Andrea
    Bertani, Cristina
    Mascari, Fulvio
    PROGRESS IN NUCLEAR ENERGY, 2021, 136
  • [27] An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow
    Gao, Jinchen
    Li, Gen
    Wang, Jinshi
    Duan, Guangtao
    Yan, Junjie
    Progress in Nuclear Energy, 2022, 149
  • [28] An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow
    Gao, Jinchen
    Li, Gen
    Wang, Jinshi
    Duan, Guangtao
    Yan, Junjie
    PROGRESS IN NUCLEAR ENERGY, 2022, 149
  • [29] Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9
    Bersano, A.
    Falcone, N.
    Bertani, C.
    De Salve, M.
    Meloni, P.
    Mascari, F.
    PROGRESS IN NUCLEAR ENERGY, 2021, 139
  • [30] Performance assessment of the two-phase pump degradation model in the relap5-3d transient safety analysis code
    Lane, Jeffrey W.
    Hochreiter, L. E.
    Aumiller, D. L., Jr.
    Kushner, R. J.
    NUCLEAR TECHNOLOGY, 2008, 161 (03) : 277 - 285