Browse > Article
http://dx.doi.org/10.1016/j.net.2019.07.029

The JFNK method for the PWR's transient simulation considering neutronics, thermal hydraulics and mechanics  

He, Qingming (Xi'an Jiaotong University, School of Nuclear Science and Technology)
Zhang, Yijun (Xi'an Jiaotong University, School of Nuclear Science and Technology)
Liu, Zhouyu (Xi'an Jiaotong University, School of Nuclear Science and Technology)
Cao, Liangzhi (Xi'an Jiaotong University, School of Nuclear Science and Technology)
Wu, Hongchun (Xi'an Jiaotong University, School of Nuclear Science and Technology)
Publication Information
Nuclear Engineering and Technology / v.52, no.2, 2020 , pp. 258-270 More about this Journal
Abstract
A new task of using the Jacobian-Free-Newton-Krylov (JFNK) method for the PWR core transient simulations involving neutronics, thermal hydraulics and mechanics is conducted. For the transient scenario of PWR, normally the Picard iteration of the coupled coarse-mesh nodal equations and parallel channel TH equations is performed to get the transient solution. In order to solve the coupled equations faster and more stable, the Newton Krylov (NK) method based on the explicit matrix was studied. However, the NK method is hard to be extended to the cases with more physics phenomenon coupled, thus the JFNK based iteration scheme is developed for the nodal method and parallel-channel TH method. The local gap conductance is sensitive to the gap width and will influence the temperature distribution in the fuel rod significantly. To further consider the local gap conductance during the transient scenario, a 1D mechanics model is coupled into the JFNK scheme to account for the fuel thermal expansion effect. To improve the efficiency, the physics-based precondition and scaling technique are developed for the JFNK iteration. Numerical tests show good convergence behavior of the iterations and demonstrate the influence of the fuel thermal expansion effect during the rod ejection problems.
Keywords
Multi-physics; Neutronics/TH/Mechanics; JFNK; Preconditioning; Transient;
Citations & Related Records
연도 인용수 순위
  • Reference
1 David E. Keyes, et al., Multiphysics simulations: challenges and opportunities, Int. J. High Perform. Comput. Appl. 27 (1) (2013) p4-p83.   DOI
2 J. Magedanz, et al., High-fidelity multi-physics system TORT-D/CTF/FRAPTRAN for light water reactor analysis, Ann. Nucl. Energy 84 (2015) p234-p243.   DOI
3 L. Holt, et al., Development of a general coupling interface for the fuel performance code TRANSURANUS-Tested with the reactor dynamics code DYN3D, Ann. Nucl. Energy 84 (2015) p73-p85.   DOI
4 M.G. Mankosa, et al., Anisotropic azimuthal power and temperature distribution as a driving force for hydrogen redistribution, in: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, American Nuclear Society, 2015.
5 Yijun Zhang, et al., Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis, Ann. Nucl. Energy 118 (2018) p220-p234.   DOI
6 Timo Ikonen, et al., Multiphysics simulation of fast transients with the FINIX fuel behaviour module 2, EPJ Nuclear Sciences & Technologie, 2016, p. p37.
7 Derek Gaston, et al., Parallel algorithms and software for nuclear, energy, and environmental applications. Part II: multiphysics software, Commun. Comput. Phys. 12 (3) (2012) p834-p865.   DOI
8 Motoe Suzuki, Hiroaki Saitou, Light Water Reactor Fuel Analysis Code FEMAXI-6 (Ver. 1). Detailed Structure and User's Manual, 2003.
9 Joseph YR. Rashid, Suresh K. Yagnik, Robert O. Montgomery, Light water reactor fuel performance modeling and multi-dimensional simulation, JOM 63 (8) (2011) p81.
10 K.J. Geelhood, et al., FRAPCON-3.4: a Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Richland, WA, 2011.
11 Youqi Zheng, Yunlong Xiao, Hongchun Wu, Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation, Nucl. Eng. Des. 320 (2017) p200-p206.   DOI
12 J.D. Hales, et al., Advanced multiphysics coupling for LWR fuel performance analysis, Ann. Nucl. Energy 84 (2015) p98-p110.   DOI
13 Vijay S. Mahadevan, Jean C. Ragusa, Vincent A. Mousseau, A verification exercise in multiphysics simulations for coupled reactor physics calculations, Prog. Nucl. Energy (2012) 12-32.
14 Han Zhang, et al., An assessment of coupling algorithms in HTR simulator TINTE, Nucl. Sci. Eng. 190 (3) (2018) 287-309.   DOI
15 E.D. Walker, B. Collins, J.C. Gehin, Jacobian-Free Newton-krylov coupling methods for nuclear reactors, in: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, 2017.
16 Chengkui Liao, Zhongsheng Xie, The coupled kinetic and thermal-hydraulic three dimensional code system NLSANMT/COBRA-IV for PWR core transient analysis, Ann. Nucl. Energy 30 (4) (2003) p405-p412.   DOI
17 Dana A. Knoll, David E. Keyes, Jacobian-free NewtoneKrylov methods: a survey of approaches and applications, J. Comput. Phys. 193 (2) (2004) p357-p397.   DOI
18 Herbert Finnemann, Aldo Galati, NEACRP 3-D LWR Core Transient Benchmark: Final Specifications, 1992.
19 Youcef Saad, Martin H. Schultz, GMRES: a generalized minimal residual algorithm for solving nonsymmetric linear systems, SIAM J. Sci. Stat. Comput. 7 (3) (1986) p856-p869.   DOI
20 Youcef Saad, Iterative Methods for Sparse Linear Systems, PWS Pub. Co., 2009.
21 A.M. Ross, R.L. Stoute, Heat Transfer Coefficient between UO 2 and Zircaloy-2. No. AECL-1552, Atomic Energy of Canada Limited, 1962.
22 Han Zhang, et al., Efficient simultaneous solution of multi-physics multi-scale nonlinear coupled system in HTR reactor based on nonlinear elimination method, Ann. Nucl. Energy 114 (2018) p301-p310.   DOI