Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project

被引:0
|
作者
Merzari, Elia [1 ]
Bolotnov, Igor [2 ]
Dinh, Nam [2 ]
Baglietto, Emilio [3 ]
Manera, Annalisa [4 ]
Shaver, Dillon [5 ]
Hassan, Yassin [6 ]
机构
[1] Penn State Univ, Dept Nucl Engn, 228 Hallowell, University Pk, PA 16802 USA
[2] North Carolina State Univ, Dept Nucl Engn, Raleigh, NC USA
[3] MIT, Dept Nucl Sci & Engn, Cambridge, MA USA
[4] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI USA
[5] Argonne Natl Lab, Nucl Sci & Engn Div, Lemont, IL USA
[6] Texas A&M Univ, Dept Nucl Engn, College Stn, TX USA
关键词
High-fidelity Simulation; Multiscale; Advanced Reactors; VALIDATION; MODEL;
D O I
10.1016/j.nucengdes.2024.113807
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
GPU-based supercomputing enables a significant advancement in Computational Fluid Dynamics (CFD) capabilities for nuclear reactors. Pre-exascale GPU-based supercomputers such as ORNL's Summit allow for the first time to perform full core CFD calculations with URANS and LES approaches. Key to this has been the development of NekRS, a novel GPU-oriented variant of Nek5000, an open-source spectral element code in development at Argonne National Laboratory. NekRS delivers peak performance for key kernels on the GPUs and good scaling performance even on CPU architectures. Recent performance measurements showed that NekRS, when running on GPUs, outperforms the CPUs by 40x. This manuscript focuses on how these calculations and novel high-resolution experimental data improve the fidelity of traditional approaches such as systems analysis codes, subchannel codes, and Reynolds-Averaged Navier-Stokes. Supercomputing simulation alone cannot impact design and safety analysis without a suitable multiscale framework. An ongoing IRP project led by Penn State is pursuing novel methods for scale bridging. We discuss details of the project, and, in particular, we review some recent progress centered on four industry-driven challenge problems.
引用
收藏
页数:16
相关论文
共 50 条
  • [1] Multiscale analysis of nuclear reactors thermal-hydraulics - the NEPTUNE project
    Bestion, D
    Guelfi, A
    HOUILLE BLANCHE-REVUE INTERNATIONALE DE L EAU, 2005, (05): : 65 - 74
  • [2] Towards more efficient implementations of multiscale thermal-hydraulics
    Gerschenfeld, Antoine
    NUCLEAR ENGINEERING AND DESIGN, 2021, 381
  • [3] Towards more efficient implementations of multiscale thermal-hydraulics
    Gerschenfeld, Antoine
    Nuclear Engineering and Design, 2021, 381
  • [4] NEW IAEA COORDINATED RESEARCH PROJECT ON THERMAL-HYDRAULICS OF SUPERCRITICAL WATER COOLED REACTORS
    Yamada, Katsumi
    Leung, Laurence
    Ambrosini, Walter
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 2, 2016,
  • [5] A KINETICS AND THERMAL-HYDRAULICS CAPABILITY FOR THE ANALYSIS OF RESEARCH REACTORS
    WOODRUFF, WL
    NUCLEAR TECHNOLOGY, 1984, 64 (02) : 196 - 206
  • [6] European research on HLM thermal-hydraulics for ADS applications
    Roelofs, F.
    de Jager, B.
    Class, A.
    Jeanmart, H.
    Schuurmans, P.
    Ciampichetti, A.
    Gerbeth, G.
    Stieglitz, R.
    Fazio, C.
    JOURNAL OF NUCLEAR MATERIALS, 2008, 376 (03) : 401 - 404
  • [7] Applications of neutron computed tomography to thermal-hydraulics research
    Lohvithee, Manasavee
    Rassame, Somboon
    Hibiki, Takashi
    PROGRESS IN NUCLEAR ENERGY, 2022, 149
  • [8] Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
    Dai T.
    Cao L.
    He Q.
    Wu H.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (01): : 136 - 145
  • [9] THERMAL-HYDRAULICS RESEARCH-AND-DEVELOPMENT FOR SLOWPOKE HEATING REACTORS
    DIMMICK, GR
    BINDNER, PE
    CHATOORGOON, V
    SCHENK, JR
    SOLLYCHIN, R
    NUCLEAR ENGINEERING AND DESIGN, 1990, 122 (1-3) : 425 - 434
  • [10] Editorial: Experimental and simulation research on nuclear reactor thermal-hydraulics
    Zhang, Luteng
    Pan, Liangming
    Wang, Jun
    Ding, Wei
    FRONTIERS IN ENERGY RESEARCH, 2022, 10