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Volume 42 Issue 5
Sep.  2021
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Liu Xiaojing, Xie Qiuxia, Chai Xiang, Cheng Xu. Status and Progress of the Multi-Physics Coupling and Multi-Scale Coupling Research for Numerical Reactors[J]. Nuclear Power Engineering, 2021, 42(5): 1-7. doi: 10.13832/j.jnpe.2021.05.0001
Citation: Liu Xiaojing, Xie Qiuxia, Chai Xiang, Cheng Xu. Status and Progress of the Multi-Physics Coupling and Multi-Scale Coupling Research for Numerical Reactors[J]. Nuclear Power Engineering, 2021, 42(5): 1-7. doi: 10.13832/j.jnpe.2021.05.0001

Status and Progress of the Multi-Physics Coupling and Multi-Scale Coupling Research for Numerical Reactors

doi: 10.13832/j.jnpe.2021.05.0001
  • Received Date: 2021-02-24
  • Rev Recd Date: 2021-03-27
  • Publish Date: 2021-09-30
  • This paper explains the basic concept of numerical reactors, and studies in detail the international research and development (R&D) projects for numerical reactors, such as the Consortium for Advanced Simulation of Light Water Reactors (CASL), European Nuclear Reactor Simulation (NURESIM) platform, and Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. It also presents a further study on and a summary of the current research status of multi-physics coupling and multi-scale coupling technology in China and other countries. In combination with the research status, this paper indicates that the focus of the numerical reactor technology development rests on the multi-physics coupling mechanism under the combined action of material corrosion, flow heat transfer and neutronics, and the development of high-fidelity coupling code based on unified grid solution.

     

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  • [1]
    廖玮,于洋,刘东. 开发数字化反应堆提升反应堆设计与研发能力[J]. 中国核工业,2016(2): 44-47+64.
    [2]
    KROPACZEK D J. Consortium for advanced simulation of light water reactors: CASL-U-2020-1974-000[R]. United States: Oak Ridge National Lab(ORNL), 2020.
    [3]
    CACUCI D G, ARAGONÉS J M, BESTION D, et al. NURESIM: a European platform for nuclear reactor simulation[C]. Luxembourg: Conference on EU Research and Training in Reactor Systems, 2006.
    [4]
    CHANARON B. Overview of the NURESAFE European project[J]. Nuclear Engineering and Design, 2017(321): 1-7.
    [5]
    VERSLUIS R M. NEAMS software verification and validation plan requirements version 0[EB/OL]. (2013-09-09)[2021-02-24]. https://www.energy.gov/ne/downloads/nuclear-energy-advanced-modeling-and-simulation-neams-software-verification-and.
    [6]
    XU Y. A matrix free Newton/Krylov method for coupling complex multi-physics subsystems[D]. West Lafayette: Purdue University, 2004.
    [7]
    冯竟超. 先进反应堆热工水力与多物理场耦合程序开发及应用研究[D]. 合肥: 中国科学技术大学, 2017.
    [8]
    ZERKAK O, KOZLOWSKI T, GAJEV I. Review of multi-physics temporal coupling methods for analysis of nuclear reactors[J]. Annals of Nuclear Energy, 2015(84): 225-233.
    [9]
    BEAM T M, IVANOV K N, BARATTA A J, et al. Nodal kinetics model upgrade in the Penn State coupled TRAC/NEM codes[J]. Annals of Nuclear Energy, 1999, 26(13): 1205-1219. doi: 10.1016/S0306-4549(99)00006-7
    [10]
    BARBER D A, WANG W, MILLER R M, et al. Application of a generalized interface module to the coupling of PARCS with both RELAP5 and TRAC-M[R]. United States: Los Alamos National Lab, 1999.
    [11]
    LIAO C, XIE Z. The coupled kinetic and thermal-hydraulic three dimensional code system NLSANMT/COBRA-IV for PWR core transient analysis[J]. Annals of Nuclear Energy, 2003, 30(04): 405-412. doi: 10.1016/S0306-4549(02)00077-4
    [12]
    KLIEM S, KOZMENKOV Y. Comparative analysis of a pump cast-down transient using the coupled code systems DYN3D-ATHLET and DYN3D-RELAP5: FZR-407[R]. Germany: Institute of Safety Research, 2003.
    [13]
    BAKANOV V V, ZHITNIK A K, MOTLOKHOV V N, et al. TDMCC Monte-Carlo package coupled with STAR-CD thermal-hydraulics code[J]. Transactions of the American Nuclear Society, 2004(91): 250-251.
    [14]
    HAN G J, JIN Y C, KIM Y, et al. Consistent comparison of Monte Carlo and whole-core transport solutions for cores with thermal feedback[C]. Chicago: PHYSOR 2004-the Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, 2004: 25-29.
    [15]
    WAATA C, SCHULENBERG T, XU C. Coupling of MCNPX with a sub-channel code for analysis of a HPLWR fuel assembly[C]. Avignon, France: International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2005.
    [16]
    LOZANO J A, JIMENEZ J, GARCÍA-HERRANZ N, et al. Development and performance of the ANDES/COBRA-III coupled system in hexagonal-z geometry[C]. New York: International Conference on Mathematics, Computational Methods and Reactor Physics, 2009.
    [17]
    史敦福,李康,秦桂明,等. 蒙卡中子输运程序JMCT和子通道热工水力程序COBRA-EN耦合计算[J]. 强激光与粒子束,2017, 29(3): 32-38.
    [18]
    SEUBERT A, LAURIEN E. The transient 3-D transport coupled code TORT-TD/ATTICA3D for high-fidelity pebble-bed HTGR analyses[J]. Transport Theory and Statistical Physics, 2012, 41(1-2): 133-152. doi: 10.1080/00411450.2012.671212
    [19]
    ZHANG D L, ZHAI Z G, RINEISKI A, et al. Couple, a time-dependent coupled neutronics and thermal-hydraulics code, and its application to MSFR[C]. Prague: Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22), 2014.
    [20]
    MARZANO M J. Approach to coupling 3-D deterministic neutron transport and full field computational fluid dynamics[D]. Gainesville: University of Florida, 2011.
    [21]
    GOMEZ-TORRES A M, SANCHEZ-ESPINOZA V H, IVANOV K, et al. DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters-Part II: comparison of different temporal schemes[J]. Annals of Nuclear Energy, 2012, 48(12): 123-129.
    [22]
    WU X, KOZLOWSKI T. Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback[C]. Charlotte: International Congress on Advances in Nuclear Power Plants, 2013.
    [23]
    GUO J, LIU S, SHANG X, et al. Versatility and stabilization improvements of full core neutronics/thermal-hydraulics coupling between RMC and CTF[J]. Nuclear Engineering and Design, 2018(332): 88-98.
    [24]
    TOTH A, KELLEY C T, SLATTERY S, et al. Analysis of anderson acceleration on a simplified neutronics/thermal hydraulics system[C]. Nashville, Tennessee, USA: Joint International Conference on Mathematics and Computation(M&C), Supercomputing in Nuclear Applications(SNA), and the Monte Carlo(MC) Method, 2015.
    [25]
    TUOMINEN R, VALTAVIRTA V, LEPPÄNEN J. Application of the Serpent–OpenFOAM coupled code system to the SEALER reactor core[C]. Cancun, Mexico: PHYSOR 2018: Reactor Physics Paving the Way towards More Efficient Systems, 2018.
    [26]
    苏光辉, 秋穗正, 田文喜. 核动力系统热工水力计算方法[M]. 北京: 清华大学出版社, 2013.
    [27]
    ANDERSON N, HASSAN Y, SCHULTZ R. Analysis of the hot gas flow in the outlet plenum of the VHTR using coupled RELAP5-3D system code and a CFD code[J]. Nuclear Engineering and Design, 2008, 238(1): 274-279. doi: 10.1016/j.nucengdes.2007.06.008
    [28]
    TURZÓ K, LEWITOWICZ M, HARAKEH M N. ENSAR, a nuclear science project for European research area[J]. Nuclear Physics News, 2015, 25(3): 3-4. doi: 10.1080/10619127.2015.1073512
    [29]
    刘余,张虹,贾宝山. 核反应堆热工水力多尺度耦合模拟初步研究[J]. 核动力工程,2010, 31(S1): 11-15.
    [30]
    贾斌,马帅,史强,等. 非能动压水堆热工水力多尺度耦合计算分析研究[J]. 核科学与工程,2018, 38(5): 763-773. doi: 10.3969/j.issn.0258-0918.2018.05.006
    [31]
    李书舟. 铅基快堆子通道耦合分析方法研究及应用[D]. 合肥: 中国科学技术大学, 2017.
    [32]
    BUONGIORNO J. Can corrosion and CRUD actually improve safety margins in LWRs?[J]. Annals of Nuclear Energy, 2014, 63(1): 9-21.
    [33]
    CHABICOVSKY M, HNIZDIL MTSENG A A, et al. Effects of oxide layer on Leidenfrost temperature during spray cooling of steel at high temperatures[J]. International Journal of Heat and Mass Transfer, 2015, 88(9): 236-246.
    [34]
    SINHA J. Effects of surface roughness, oxidation level, and liquid subcooling on the minimum film boiling temperature[J]. Experimental Heat Transfer, 2003, 16(1): 45-60. doi: 10.1080/08916150390126478
    [35]
    SALKO R K, BLYTH T, DANCES C, et al. CASL Consortium for advanced simulation of LWRs: L3: PHI. VCS. P9.02CTF validation: CASL-U-2014-0169- 000[R]. USA: Oak Ridge National Laboratory and Pennsylvania State University, 2014.
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