Improvement of ALFRED thermal hydraulics through experiments and numerical studies (English)
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In:
Nuclear Engineering and Design
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409
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2023
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Improvement of ALFRED thermal hydraulics through experiments and numerical studies
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Contributors:Caramello, M. ( author ) / Frignani, M. ( author ) / Grasso, G. ( author ) / Tarantino, M. ( author ) / Martelli, D. ( author ) / Lorusso, P. ( author ) / Piazza, I. Di ( author )
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Published in:
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2023-04-28
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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 409
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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Improving production and prediction of the flow regimes, pressure drop, and void fraction in the perforated horizontal wellboreKareem, Hasanain J. / Hasini, Hasril / Abdulwahid, Mohammed A. et al. | 2023
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Key elements for proper development and implementation of severe accident management guidance/guidelines – SAMGVayssier, G. / Lutz, R.J. Jr / Harter, R.L. / Gabor, J. et al. | 2023
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Thermo-fluid dynamic analysis of HLM pool. Circe experimentsMartelli, D. / Marinari, R. / Di Piazza, I. / Lorusso, P. / Tarantino, M. et al. | 2023
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Study on diffusion and migration characteristics of impurities in secondary side of simplified u-tube steam generatorLi, Meng / Cheng, Kun / Wen, Jiming / Tian, Ruifeng et al. | 2023
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Thermomechanical analysis and modeling of involute-shaped fuel plates using the Cheverton–Kelley experiments for the High Flux Isotope ReactorSitek, Marta / Shehu, Kaltrina / Jain, Prashant K. / Bergeron, Aurélien / Licht, Jeremy / Reiter, Christian et al. | 2023
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CFD Uncertainty Quantification using stochastic spectral methods—Exemplary application to a buoyancy-driven mixing processWenig, Philipp J. / Kelm, Stephan / Klein, Markus et al. | 2023
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Development of a coupled neutronics-CFD system for 540 MWE Indian Pressurized heavy water reactors (IPHWRs) and verification with slow online refuelling transientJha, Alok / Gupta, Anurag et al. | 2023
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Validation of the fully-analytical solution with temperature superposition for the nuclear waste repositoryXu, Xun / He, Luqiang / Sun, De'an / Zhou, Xiangyun et al. | 2023
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A simple correlation to estimate agglomerated debris formation based on experiments of melt jet-breakup using a metallic meltIwasawa, Yuzuru / Sugiyama, Tomoyuki / Kaneko, Akiko et al. | 2023
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Review and main outcomes from the experimental program carried on the plateau facilityGuenadou, D. / Aubert, P. / Descamps, J.P. / Cachon, L. / Gilardi, T. et al. | 2023
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Experimental study on fuel depressurization and its effect on dispersionLatimer, Griffen / Marcum, Wade R. / Jones, Warren F. et al. | 2023
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Nuclear reactor Thermal-Hydraulics Special and prospective topical areasSánchez, Miguel / Riznic, Jovica et al. | 2023
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Analysis of natural convection heat transfer and solidification within a corium simulantRezaee, Mahsa / David, Dijo / Lightstone, Marilyn / Tullis, Stephen et al. | 2023
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Studies of liquid metal boiling in fuel assemblies of fast reactors in accident conditionsSorokin, A.P. / Kuzina, Yu.A. / Sorokin, G.A. / Denisova, N.A. et al. | 2023
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On the importance of consistency of multiple-level modeling of multiphase flow in reactor systemsPodowski, Michael Z. et al. | 2023
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SIMMER modelling of accident initiation phase in sodium fast reactorsChen, Xue-Nong / Rineiski, Andrei et al. | 2023
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Structural integrity assessment of a closure head of a PWR reactor pressure vessel under pressurized thermal shockNaweed, Muhammad / Murtaza, Usman Tariq / Siddique, Waseem et al. | 2023
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Cooldown of a water-cooled reactor during the natural circulation mode using decay heat of the core and a low-power steam turbineYurin, V.E. / Egorov, A.N. / Bashlykov, D.O. et al. | 2023
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Fundamental and applied investigations of the liquid-metal cooled fast reactor thermal hydraulics (achieved results and further investigation issues)Kuzina, Yu.A. / Sorokin, A.P. et al. | 2023
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On the role of simulation codes in regulatory activities. Challenges and R&D needsSánchez, M. / Mendizábal, R. / Pelayo, F. / Meléndez, E. / Izquierdo, J.M. / Hortal, J. / Pérez, J. et al. | 2023
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Improvement of ALFRED thermal hydraulics through experiments and numerical studiesCaramello, M. / Frignani, M. / Grasso, G. / Tarantino, M. / Martelli, D. / Lorusso, P. / Piazza, I. Di et al. | 2023
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Effect of xenon removal rate on load following in high power thermal spectrum Molten-Salt Reactors (MSRs)Dunkle, Nicholas / Chvala, Ondrej et al. | 2023
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Numerical analyses of the CIRCE-THETIS facility by mean of STH and CFD codesStefanini, Pietro / Pucciarelli, Andrea / Forgione, Nicola / Di Piazza, Ivan / Martelli, Daniele et al. | 2023
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Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using PythonEmampour, Mohammad Hassan / Ghafari, Mohsen et al. | 2023
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Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundleCiurluini, C. / Narcisi, V. / Giannetti, F. / Lorusso, P. / Tarantino, M. / Caruso, G. et al. | 2023
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A new approach to calculating the drag force of the scoop in the gas centrifugeGhazanfari, Valiyollah / Shadman, Mohammad Mahdi / Mansourzadeh, Fatemeh et al. | 2023
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Editorial Board| 2023