Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology |
Li, Yuanming
(Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laborotary of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Yuan, Pan (Science and Technology on Reactor System Design Technology Laboratory) Ren, Quan-yao (Science and Technology on Reactor System Design Technology Laboratory) Su, Guanghui (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laborotary of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) Yu, Hongxing (Science and Technology on Reactor System Design Technology Laboratory) Wang, Haoyu (Science and Technology on Reactor System Design Technology Laboratory) Zheng, Meiyin (Science and Technology on Reactor System Design Technology Laboratory) Wu, Yingwei (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laborotary of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) Ding, Shurong (Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan Univeristy) |
1 | R.L. Williamson, J.D. Hales, S.R. Novascone, et al., Multidimensional multiphysics simulation of nuclear fuel behavior [J], J. Nucl. Mater. 423 (1-3) (2012) 149-163. DOI |
2 | Y. He, P. Chen, Y. Wu, et al., Preliminary evaluation of U3Si2 -FeCrAl fuel performance in light water reactors through a multi-physics coupled way [J], Nucl. Eng. Des. 328 (2018) 27-35. DOI |
3 | R. Liu, W. Zhou, Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor [J], Ann. Nucl. Energy 109 (2017) 298-309. DOI |
4 | J.C. Kennedy, Development and Experimental Benchmarking of Numeric Fluid Structure Interaction Models for Research Reactor Fuel Analysis (PhD Dissertation), University of Missouri, 2015. |
5 | Fraunhofer SCAI Inc., MpCCI Documentation- Release 4, vol. 4, 2015, p. 2. |
6 | ANSYS Inc, ANSYS FLUENT Documentation - Release 15.0, 2014. |
7 | Y. Deng, Y. Wu, D. Zhang, et al., Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel [J], Prog. Nucl. Energy 95 (2017) 8-22. DOI |
8 | W. Fan, C. Peng, Y. Guo, et al., CFD study on inlet flow blockage accidents in rectangular fuel assembly [J], Nucl. Eng. Des. 292 (2015) 177-186. DOI |
9 | Aaren Rice, Intercode advanced fuels and cladding comparison using BISON, FRAPCON, and FEMAXI fuel performance codes, University of South Carolina, 2015. |
10 | G. Daxin, H. Shanfang, W. Guanbo, et al., Heat transfer calculation on plate-type fuel assembly of high flux research reactor[J], Science & Technology of Nuclear Installations 2015 (2015) 1-13. |
11 | L. Li, D. Fang, D. Zhang, et al., Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements[J], Ann. Nucl. Energy 134 (2019) 284-298. DOI |
12 | J.G. Mantecon, M.M. Neto, Numerical analysis on stability of nuclear fuel plates with inlet support comb [J], Nucl. Eng. Des. 342 (2019) 240-248. DOI |
13 | John C. Kennedy, Gary L. Solbrekken, Coupled fluid structure interaction (FSI) modeling of parallel plate Assemblies [J], Am. Soc. Mech. Eng. (2011) 159-167. |
14 | Y. Zhao, X. Gong, S. Ding, Simulation of the irradiation-induced thermo-mechanical behaviors evolution in monolithic U-Mo/Zr fuel plates under a heterogeneous irradiation condition [J], Nucl. Eng. Des. 285 (2015) 84-97. DOI |
15 | X. Gong, Y. Zhao, S. Ding, A new method to simulate the micro-thermomechanical behaviors evolution in dispersion nuclear fuel elements [J], Mech. Mater. 77 (2014) 14-27. DOI |
16 | D.M. Perez, M.A. Lillo, G.S. Chang, G.A. Roth, N.E. Woolstenhulme, D.M. Waches, RERTR-9 Irradiation Summary Report, Idaho National Laboratory Report INL/EXT-10-18421, 2011. |
17 | J.G. Mantecon, M.M. Neto, Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions, Nucl. Eng. Des. 333 (2018) 76-86. DOI |
18 | Z. Ma, R. Chen, M. Tian, et al., Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology [J], Ann. Nucl. Energy 112 (2018) 71-83. DOI |
19 | Y.S. Kim, G.L. Hofman, J.S. Cheon, et al., Fission induced swelling and creep of UeMo alloy fuel[J], J. Nucl. Mater. 437 (s 1-3) (2013) 37-46. DOI |
20 | F. Yan, et al., Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates [J], J. Nucl. Mater. 524 (2019) 209-217. DOI |
21 | A.M. Phillippe, L. Ott, K. Clarno, et al., Analysis of the IFA-432, IFA-597, and IFA-597mox Fuel Performance Experiments by FRAPCON-3.4. ORNL/TM-2012/195, Oak Ridge National Laboratory, 2012. |
22 | J. Yoo, Y. Oka, Y. Ishiwatari, et al., Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code [J], Ann. Nucl. Energy 33 (17/18) (2006) 1379-1390. DOI |