CFD simulation and analysis of reactor integral hydraulic tests (English)
- New search for: Chen, Shuo
- Further information on Chen, Shuo:
- https://orcid.org/0000-0001-6550-9498
- New search for: Gu, Hanyang
- New search for: Chen, Shuo
- Further information on Chen, Shuo:
- https://orcid.org/0000-0001-6550-9498
- New search for: Gu, Hanyang
In:
Annals of Nuclear Energy
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135
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2019
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ISSN:
- Article (Journal) / Electronic Resource
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Title:CFD simulation and analysis of reactor integral hydraulic tests
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Contributors:Chen, Shuo ( author ) / Gu, Hanyang ( author )
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Published in:Annals of Nuclear Energy ; 135
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2019-07-27
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 135
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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Solution of one-group space- and time-dependent neutron kinetics equations for a reflected slab reactorMaleki, Bahram R. / Goluoglu, Sedat / Cubukcu, Erol / Tombakoglu, Mehmet et al. | 2019
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Neutron spectrum unfolding of the multiple activation foils based on sparse representationLiu, Bin / Yang, Hongrun / Lv, Huanwen / Li, Lan / Jing, Futing / Liu, Jiajia / Wang, Sheng et al. | 2019
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Performance and deterioration of forward osmosis membrane exposed to various dose of gamma-ray irradiationLiu, Xiaojing / Wu, Jinling / Hou, Li-an / Wang, Jianlong et al. | 2019
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A multi-scale and multi-physics approach to main steam line break accidents using coupled MASTER/CUPID/MARS codePark, Ik Kyu / Lee, Jae Ryong / Choi, Yong Hee / Kang, Doo Hyuk et al. | 2019
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The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRsMorrison, S.L. / Parks, G.T. et al. | 2019
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Theoretical comparative study of t tests and nonparametric tests for final status surveys of MARSSIM at decommissioning sitesSohn, Wook / Jeong, Meeseon / Jeong, Kahee et al. | 2019
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Effects of compensating for fuel losses during the melt-refining process for a small CANDLE reactorHoang, Van Khanh / Nishiyama, Jun / Obara, Toru et al. | 2019
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Development of a three-field mechanistic model for dryout prediction in annular flowGui, Minyang / Tian, Wenxi / Wu, Di / Chen, Ronghua / Su, G.H. / Qiu, Suizheng et al. | 2019
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Influence of the spatial Pu variation for evaluating the Pu content in spent nuclear fuel using Support Vector RegressionWoo, Seung Min / Kim, Hyeonmin / Chirayath, Sunil S. et al. | 2019
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Radial distributions of power and fuel temperature in annular U3Si2 fuel with FeCrAl claddingChen, Shengli / Ge, Yulin / Zhong, Yao / Yuan, Cenxi et al. | 2019
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Preliminary surface soil area factor for elevated residual radioactivity of Kori Unit 1 considering adjacent Unit 2Byon, Jihyang / Park, Sangjune / Ahn, Seokyoung et al. | 2019
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A radiation avoiding algorithm of path optimization for radiation protection of workers and robotsTan, Ke / Li, Mengkun / Gu, Haixia / Yang, Ming et al. | 2019
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Computational flow and heat transfer design and analysis for 1/12 gas-cooled space nuclear reactorMeng, Tao / Cheng, Kun / Zhao, Fulong / Xia, Chenchao / Tan, Sichao et al. | 2019
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An iterative fission matrix scheme for calculating steady-state power and critical control rod position in a TRIGA reactorTopham, Tyler J. / Rau, Adam / Walters, William J. et al. | 2019
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New analytical formulations for the Doppler broadening function and interference term based on Kaniadakis distributionsde Abreu, Willian V. / Gonçalves, Alessandro C. / Martinez, Aquilino S. et al. | 2019
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Numerical study of enhanced and deteriorated heat transfer phenomenon in supercritical pipe flowSahu, Suresh / Vaidya, Abhijeet M. et al. | 2019
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Nuclear material input accountancy with a representative sampling methodYoo, Tae-Sic / Westphal, Brian R. / Carney, Kevin P. et al. | 2019
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Investigation of CMT behavior between the ATLAS and SMART-ITL testsKim, Yeon-Sik / Kang, Kyoung-Ho / Park, Hyun-Sik et al. | 2019
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Application of total variation denoising in nuclear power plant signal pre-processingYang, Bo / Xia, Hong / Annor-Nyarko, M. / Wang, Zhichao et al. | 2019
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Editorial Board| 2019
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Analyses of LOFT LP-FW-1 using SPACE codeChoi, Chiwoong / Ha, Kwi-seok / Kim, Kyung Doo et al. | 2019
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On a measurement approach to support evaluation of thermal scattering law dataHawari, Ayman I. et al. | 2019
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Optimization of software development life cycle quality for NPP safety software based on a risk-cost modelLee, Sang Hun / Lee, Seung Jun / Koo, Seo Ryong / Varuttamaseni, Athi / Yue, Meng / Li, Ming / Cho, Jaehyun / Kang, Hyun Gook et al. | 2019
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Feasibility study of thorium-fueled molten salt reactor with application in radioisotope productionZheng, Gangyang / Wang, Jipu / Wu, Huali / Chen, Sijuan / Fu, Wen / Zhang, Min / Wang, Ziguan / Zhang, Yunhuang et al. | 2019
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Publisher’s Note| 2019
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Development of 3-D parallel first-collision source method for discrete ordinate code JSNT-SYang, Chao / Cheng, Tangpei / Deng, Li / Li, Zhipeng / Wen, Lili et al. | 2019
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Validation of the BERKUT fuel rod module against mixed nitride fuel experimental dataVeprev, D.P. / Boldyrev, A.V. / Chernov, S.Yu. et al. | 2019
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Experimental and numerical investigation for the geometrical parameters effect on the labyrinth-seal flow characteristics of fast reactor fuel assemblyQin, Haiqi / Lu, Daogang / Zhong, Dawen / Wang, Yu / Song, Yi et al. | 2019
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The collimator shape design of segmented gamma-ray scanning for radioactive wasteSuxia, Hou / Jijun, Luo / Rusong, Li / Yongcang, Wang et al. | 2019
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Research on the on-the-fly homogenization method based on RMC code for criticality calculationsYuan, Yuan / Xing, Ji / Huo, Xiaodong / Wang, Kan et al. | 2019
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Experimental research on subcooled boiling heat transfer for natural circulation flow in a vertical 3 × 3 rod bundleTian, Chunping / Liu, Yiwen / Meng, Haibo / Zhu, Zhiqiang / Wang, Jianjun / Yan, Changqi et al. | 2019
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Analyses of operation performance of advanced secondary passive residual heat removal system in PWRLi, Liangguo / Su, Qianhua / Yu, Jianming / Lu, Donghua / Ju, Peng / Hao, Chenyu / Wu, Xiaohang / Zhu, Feng et al. | 2019
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An analytical discrete ordinates nodal solution to the two-dimensional adjoint transport problemBarichello, L.B. / Pazinatto, C.B. / Rui, K. et al. | 2019
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Variable coefficient depletion equations – Reference solution based on Rational Approximation MethodsHuang, Kai / Fu, Xuedong / Ying, Yangjun / Zhu, Shengdong et al. | 2019
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Fractional-order particle swarm based multi-objective PWR core loading pattern optimizationZameer, Aneela / Muneeb, Muhammad / Mirza, Sikander M. / Raja, Muhammad Asif Zahoor et al. | 2019
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Conceptual study on a novel method for detecting nuclear material using a neutron sourceKomeda, Masao / Toh, Yosuke et al. | 2019
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Editorial: A preface to the special issue on “PHYSOR-2018: Reactor Physics Paving the Way Towards More Efficient Systems, 22–26 April 2018, Cancun, Mexico”François, Juan-Luis / Alonso, Gustavo / Valle, Edmundo del / Maldonado, G. Ivan et al. | 2019
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Development of the integrated parallelism strategy for large scale depletion calculation in the Monte Carlo code RMCLiu, Shichang / Liang, Jingang / Wang, Kan / Chen, Yixue et al. | 2019
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Analysis of fluctuation and breakdown characteristics of liquid film on corrugated plate wallWang, Bo / Chen, Bowen / Li, Ru / Tian, Ruifeng et al. | 2019
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The technology of micro heat pipe cooled reactor: A reviewYan, B.H. / Wang, C. / Li, L.G. et al. | 2019
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The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part I: PWRsMorrison, S.L. / Parks, G.T. et al. | 2019
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A fuzzy-logic-based pressure setpoint modification method for pressurized water reactor pressurizersWang, Pengfei / Wan, Jiashuang / Wu, Shifa / Zhao, Fuyu et al. | 2019
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Overlapping communication and computation of GPU/CPU heterogeneous parallel spatial domain decomposition MOC methodLiang, Liang / Zhang, Qian / Song, Peitao / Zhang, Zhijian / Zhao, Qiang / Wu, Hongchun / Cao, Liangzhi et al. | 2019
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Study on the water seal formation process in advanced PWR pressurizer using CFD methodWang, Xi / Wang, Mingjun / Zhang, Jing / Wu, Yingwei / Tian, Wenxi / Su, G.H. / Qiu, Suizheng et al. | 2019
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Second-order adjoint sensitivity analysis of a general ratio of functionals of the forward and adjoint fluxes in a multiplying nuclear system with sourceCacuci, Dan Gabriel et al. | 2019
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Implementation of the CPU/GPU hybrid parallel method of characteristics neutron transport calculation using the heterogeneous cluster with dynamic workload assignmentSong, Peitao / Zhang, Zhijian / Zhang, Qian / Liang, Liang / Zhao, Qiang et al. | 2019
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An approximation function model for solving effective radiative heat transfer in packed bedWu, Hao / Gui, Nan / Yang, Xingtuan / Tu, Jiyuan / Jiang, Shengyao et al. | 2019
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Status of computational fluid dynamics for in-vessel retention: Challenges and achievementsShams, A. / Dovizio, D. / Zwijsen, K. / Le Guennic, C. / Saas, L. / Le Tellier, R. / Peybernes, M. / Bigot, B. / Skrzypek, E. / Skrzypek, M. et al. | 2019
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Experimental study of heat transfer outside C-shaped tube in water tankLiu, Yanbin / Wang, Xuesheng / Men, Qiming / Meng, Xiangyu et al. | 2019
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CFD simulation and analysis of reactor integral hydraulic testsChen, Shuo / Gu, Hanyang et al. | 2019
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CFD analysis of intra and inter fuel assembly mixingBieder, Ulrich / Genrault, Clarisse et al. | 2019
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A non-linear stability monitor for boiling water reactorsOlvera-Guerrero, Omar Alejandro / Prieto-Guerrero, Alfonso / Espinosa-Paredes, Gilberto et al. | 2019
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Phase-frequency characteristic based measurement of sodium flow rate using PMSF with embedded bluff bodyYan, Xiao-Xue / Xu, Ke-Jun / Yu, Xin-Long / Xu, Wei / Wu, Jian-Ping / Xiong, Wei et al. | 2019
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Validation of ENDF/B-VIII thermal neutron scattering data of heavy water by differential cross section measurements at various temperaturesLi, G. / Bentoumi, G. / Hartling, K. / Molnar, I. / Neggers, C. / Rogge, R. / Yamani, Z. et al. | 2019
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On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficientsSiefman, D. / Hursin, M. / Aufiero, M. / Bidaud, A. / Pautz, A. et al. | 2019
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Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometriesGarcía, Manuel / Ferraro, Diego / Valtavirta, Ville / Tuominen, Riku / Imke, Uwe / Leppänen, Jaakko / Sanchez-Espinoza, Victor et al. | 2019
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Application of a 3D model in the transient system analysis of sodium-cooled fast reactorGe, Li / Lu, Tianyu / Shan, Jianqiang / Liu, Dong et al. | 2019
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Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assemblyJeong, Yeong Shin / Kim, Ji Yong / Bang, In Cheol et al. | 2019
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3-Way coupled thermohydraulic-discrete element-neutronic simulation of solid fuel, molten salt reactorMardus-Hall, Robert / Ho, Mark / Pastrello, Andrew / Yeoh, Guan et al. | 2019
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Feasibility assessment of using external neutron and gamma radiation measurements for monitoring the state of fuel assemblies in dry storage casksRachamin, Reuven / Hampel, Uwe et al. | 2019
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Sensitivity and uncertainty analysis of the vessel lower head failure mode and melt release conditions in Nordic BWR using MELCOR codeGalushin, Sergey / Kudinov, Pavel et al. | 2019
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Experimental research on assembly section stiffness and bending stiffness for sodium-cooled fast reactorMa, Zehua / Yang, Hongyi / Ma, Zhenhui / Wu, Yingwei / Lu, Kailin / Wang, Kaiqiang / Chen, Hongen / Su, G.H. / Chen, Zhenmao et al. | 2019