3D numerical study of LBE-cooled fuel assembly in MYRRHA using SIMMER-IV code (English)
- New search for: Li, Rui
- New search for: Chen, Xue-Nong
- New search for: Andriolo, Lena
- New search for: Rineiski, Andrei
- New search for: Li, Rui
- New search for: Chen, Xue-Nong
- New search for: Andriolo, Lena
- New search for: Rineiski, Andrei
In:
Annals of Nuclear Energy
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104
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42-52
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2017
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ISSN:
- Article (Journal) / Electronic Resource
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Title:3D numerical study of LBE-cooled fuel assembly in MYRRHA using SIMMER-IV code
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Contributors:Li, Rui ( author ) / Chen, Xue-Nong ( author ) / Andriolo, Lena ( author ) / Rineiski, Andrei ( author )
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Published in:Annals of Nuclear Energy ; 104 ; 42-52
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2017-02-11
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Size:11 pages
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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 104
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.
- 1
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Conceptual design of a sub-critical Pb-cooled Accelerator Driven System (ADS) fuelled by (Th-LEU)Glinatsis, G. / Carta, M. / Gugiu, D. et al. | 2017
- 9
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Verification of AP1000® low-margin PRA sequences based on best-estimate calculationsQueral, C. / Montero-Mayorga, J. / Rivas-Lewicky, J. / Rebollo, M.J. et al. | 2017
- 28
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Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz ReactorGhione, Alberto / Noel, Brigitte / Vinai, Paolo / Demazière, Christophe et al. | 2017
- 42
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3D numerical study of LBE-cooled fuel assembly in MYRRHA using SIMMER-IV codeLi, Rui / Chen, Xue-Nong / Andriolo, Lena / Rineiski, Andrei et al. | 2017
- 53
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Improving fuel utilization in SmAHTR with spectral shift control design: Proof of conceptKotlyar, D. / Lindley, B.A. / Mohamed, H. et al. | 2016
- 64
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A forward-backward coupled source term estimation for nuclear power plant accident: A case study of loss of coolant accident scenarioSun, Sida / Li, Hong / Fang, Sheng et al. | 2017
- 75
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Investigation of flow through multi-stage restricting orificesAraoye, Abdulrazaq A. / Badr, Hasan M. / Ahmed, Wael H. et al. | 2017
- 91
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Comparison and analysis on transient characteristics of integral pressurized water reactorsZhang, Guoxu / Xie, Heng et al. | 2017
- 103
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Developing and investigating a pure Monte-Carlo module for transient neutron transport analysisMylonakis, Antonios G. / Varvayanni, M. / Grigoriadis, D.G.E. / Catsaros, N. et al. | 2016
- 113
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A 3-D simulation tool for hydrogen detonation during severe accident and its applicationHuang, T. / Zhang, Y.P. / Tian, W.X. / Su, G.H. / Qiu, S.Z. et al. | 2017
- 124
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Uncertainty analysis of assembly and core-level calculations with application to CASMO-4E and SIMULATE-3Pusa, Maria / Isotalo, Aarno et al. | 2017
- 132
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Covariance matrices of the hydrogen neutron cross sections bound in light water for the JEFF-3.1.1 neutron libraryNoguere, G. / Scotta, J.P. / De Saint Jean, C. / Archier, P. et al. | 2017
- 146
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Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFsDeng, Yangbin / Wu, Yingwei / Qiu, Bowen / Zhang, Dalin / Wang, Mingjun / Tian, Wenxi / Qiu, Suizheng / Su, G.H. et al. | 2017
- 157
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Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—I: Scheme of OLVTLi, Yankai / Lin, Meng / Yang, Zongwei / Hou, Yousheng / Yang, Yanhua et al. | 2017
- 166
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Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—Ⅱ: DCS-testing methodsLin, Meng / Li, Yankai / Yang, Zongwei / Hou, Yousheng / Yang, Yanhua et al. | 2017
- 178
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Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media methodChen, Ronghua / Tian, Maolin / Chen, Sen / Tian, Wenxi / Su, G.H. / Qiu, Suizheng et al. | 2017
- 191
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MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) facilityPatel, Vishal K. / Reichenberger, Michael A. / Roberts, Jeremy A. / Unruh, Troy C. / McGregor, Douglas S. et al. | 2017
- 197
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The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannelsHammouda, N. / Rao, Y.F. et al. | 2017
- 214
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Development of whole core pin-by-pin transport theory model in hexagonal geometryKhan, Suhail Ahmad / Kannan, Umasankari / Jagannathan, V. et al. | 2017
- 229
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On the solution of the SN multigroup kinetics equations in multilayer slabsSegatto, C.F. / Tomaschewski, F.K. / Barros, R.C. / Vilhena, M.T. et al. | 2017
- 237
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Determining the minimum required uranium carbide content for HTGR UCO fuel kernelsMcMurray, Jacob W. / Lindemer, Terrence B. / Brown, Nicholas R. / Reif, Tyler J. / Morris, Robert N. / Hunn, John D. et al. | 2017
- 243
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An experimental validation of Feynman-Alpha Method’s Bunching Technique in the IPEN/MB-01 Nuclear ReatorAlves, L.F.M. / Andrade, D.A. / Dos Santos, A. et al. | 2016
- 247
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Natural frequencies of a CANDU fuel stringFadaee, M. / Yu, S.D. et al. | 2017
- 256
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Integrated CFD investigation of heat transfer enhancement using multi-tray core catcher in SFRRakhi / Sharma, Anil Kumar / Velusamy, K. et al. | 2017
- 267
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FITXS: A fast and flexible burn-up scheme based on the fitting of one-group cross-sectionsHalász, Máté / Szieberth, Máté / Fehér, Sándor et al. | 2017
- 282
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A proposal on multi-response CADIS method to optimize reduction of regional variances in hybrid Monte Carlo simulationKim, Do Hyun / Kim, Song Hyun / Shin, Chang Ho / Kim, Gee Suck / Sun, Gwang Min / Seo, Bo Kyun et al. | 2016
- 291
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Study on flow characteristics in an open two-phase natural circulation loopYan, Xiao / Fan, Guangming / Sun, Zhongning et al. | 2016
- IFC
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Editorial board| 2017