Development and validation of a fast sub-channel code for LWR multi-physics analyses

被引:11
|
作者
Chaudri, Khurrum Saleem [1 ]
Kim, Jaeha [1 ,2 ]
Kim, Yonghee [1 ]
机构
[1] Korea Adv Inst Sci & Technol, Dept Nucl & Quantum Engn, 291 Daehak Ro, Daejeon 34141, South Korea
[2] PIEAS, Dept Nucl Engn, Islamabad 45650, Pakistan
基金
新加坡国家研究基金会;
关键词
Sub-channel; LWR; PSBT; Thermal hydraulics; Multi-physics analyses; START;
D O I
10.1016/j.net.2019.02.017
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
A sub-channel solver, named Steady and Transient Analyzer for Reactor Thermal hydraulics (START), has been developed using the homogenous model for two-phase conditions of light water reactors. The code is developed as a fast and accurate TH-solver for coupled and multi-physics calculations. START has been validated against the NUPEC PWR Sub-channel and Bundle Test (PSBT) database. Tests like single-channel quality and void-fraction for steady state, outlet fluid temperature for steady state, rod-bundle quality and void-fraction for both steady state and transient conditions have been analyzed and compared with experimental values. Results reveal a good accuracy of solution for both steady state and transient scenarios. Axially different values for turbulent mixing coefficient are used based on different grid-spacer types. This provides better results as compared to using a single value of turbulent mixing coefficient. Code-to-code evaluation of PSBT results by the START code compares well with other industrial codes. The START code has been parallelized with the OpenMP algorithm and its numerical performance is evaluated with a large whole PWR core. Scaling study of START shows a good parallel performance. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:1218 / 1230
页数:13
相关论文
共 50 条
  • [31] On the validation of variable fidelity multi-physics simulations
    Patterson, Eann A.
    Whelan, Maurice P.
    JOURNAL OF SOUND AND VIBRATION, 2019, 448 : 247 - 258
  • [32] A Multi-Physics Model of the VJFET With a Lateral Channel
    Morel, Herve
    Hamieh, Youness
    Tournier, Dominique
    Robutel, Remi
    Dubois, Fabien
    Risaletto, Damien
    Martin, Christian
    Bergogne, Dominique
    Buttay, Cyril
    Meuret, Regis
    PROCEEDINGS OF THE 2011-14TH EUROPEAN CONFERENCE ON POWER ELECTRONICS AND APPLICATIONS (EPE 2011), 2011,
  • [33] Multi-physics code system with improved feedback modeling
    Yilmaz, Mine O.
    Avramova, Maria N.
    Andersen, Jens G. M.
    PROGRESS IN NUCLEAR ENERGY, 2017, 98 : 94 - 108
  • [34] A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel
    Sartori, Alberto
    Cammi, Antonio
    Luzzi, Lelio
    Rozza, Gianluigi
    ANNALS OF NUCLEAR ENERGY, 2016, 87 : 198 - 208
  • [35] Development of multi-physics code systems based on the reactor dynamics code DYN3D
    Kliem, S.
    Gommlich, A.
    Grahn, A.
    Rohde, U.
    Schuetze, J.
    Frank, T.
    Gomez, A.
    Sanchez, V.
    KERNTECHNIK, 2011, 76 (03) : 160 - 165
  • [36] Extension of the sub-channel code ANTEO plus to the mixed convection regime
    Lodi, F.
    Grasso, G.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 322 : 368 - 378
  • [37] Multi-physics code coupling methodology for the simulation of accidental transients in sodium cooled fast reactors
    Billo, Georis
    Li, Simon
    Velardo, Heloise
    ANNALS OF NUCLEAR ENERGY, 2024, 202
  • [38] Validation of Multi-Physics Coupling Code for Unsteady Reacting Swirling Flow in Solid Fuel Ramjet
    Musa, Omer
    Chen Xiong
    Zhou Changsheng
    Zhu Min
    Musa, Omer
    2017 2ND INTERNATIONAL CONFERENCE ON FRONTIERS OF SENSORS TECHNOLOGIES (ICFST), 2017, : 86 - 89
  • [39] Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
    Nikitin, Konstantin
    Clifford, Ivor
    Dokhane, Abdulhamid
    Ferroukhi, Hakim
    NUCLEAR ENGINEERING AND DESIGN, 2022, 389
  • [40] Validation of the sub-channel code F-COBRA-TF Part II.: Recalculation of void measurements
    Glueck, M.
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (09) : 2317 - 2327