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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 258 - 270 (13page)
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초록· 키워드
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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 developedfor the nodal method and parallel-channelTH 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 therations and demonstrate the influence of the fuel thermal expansion effect during the rod ejection problems
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참고문헌 (22)
참고문헌 신청
David E. Keyes / 2013 / Multiphysics simulations: challenges and opportunities / Int. J. High Perform. Comput. Appl 27(1)
J. Magedanz / 2015 / High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis / Ann. Nucl. Energy 84:234~243
L. Holt / 2015 / Development of a general coupling interface for the fuel performance code TRANSURANUSeTested with the reactor dynamics code DYN3D / Ann. Nucl. Energy 84:73~85
M. G. Mankosa / 2015 / Anisotropic azimuthal power and temperature distribution as a driving force for hydrogen redistribution / 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 2015
Yijun Zhang / 2018 / Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis / Ann. Nucl. Energy 118:220~234
J. Magedanz / 2015 / High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis / Ann. Nucl. Energy 84:234~243
L. Holt / 2015 / Development of a general coupling interface for the fuel performance code TRANSURANUSeTested with the reactor dynamics code DYN3D / Ann. Nucl. Energy 84:73~85
M. G. Mankosa / 2015 / Anisotropic azimuthal power and temperature distribution as a driving force for hydrogen redistribution / 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 2015
Yijun Zhang / 2018 / Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis / Ann. Nucl. Energy 118:220~234
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