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Volume 206

Number 2

Interface-Resolved Simulations of Reactor Flows

Jun Fang, Joseph J. Cambareri, Mengnan Li, Nadish Saini, Igor A. Bolotnov

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 133-149

Critical Review / dx.doi.org/10.1080/00295450.2019.1620056

Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

Katrien Van Tichelen, Graham Kennedy, Fabio Mirelli, Alessandro Marino, Antonio Toti, Davide Rozzia, Edoardo Cascioli, Steven Keijers, Philippe Planquart

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 150-163

Critical Review / dx.doi.org/10.1080/00295450.2019.1614803

Direct Numerical Simulation and Wall-Resolved Large Eddy Simulation in Nuclear Thermal Hydraulics

Iztok Tiselj, Cedric Flageul, Jure Oder

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 164-178

Critical Review / dx.doi.org/10.1080/00295450.2019.1614381

Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly

Graham Kennedy, Katrien Van Tichelen, Julio Pacio, Ivan Di Piazza, Heleen Uitslag-Doolaard

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 179-190

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620539

Study on Reactor Vessel Air Cooling for Westinghouse Lead Fast Reactor

Jun Liao, Dan Utley

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 191-205

Technical Paper / dx.doi.org/10.1080/00295450.2019.1599614

Development of Mechanistic Source Term Analysis Tool SAS4A-FATE for Lead- and Sodium-Cooled Fast Reactors

T. Q. Hua, S. J. Lee, J. Liao, A. Moisseytsev, P. Ferroni, A. Karahan, C. Y. Paik, A. M. Tentner, T. Sofu

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 206-217

Technical Paper / dx.doi.org/10.1080/00295450.2019.1598715

On the Fluid Structure Interactions of a Wire-Wrapped Pin Bundle

C. A. Nixon, W. R. Marcum, K. M. Steer, R. B. Jackson, M. G. Martin, A. W. Weiss

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 218-230

Technical Paper / dx.doi.org/10.1080/00295450.2019.1649583

Experimental and Numerical Characterization of the Flow Field at the Core Entrance of a Water Model of a Heavy Liquid Metal–Cooled Reactor

Philippe Planquart, Chiara Spaccapaniccia, Giacomo Alessi, Sophia Buckingham, Katrien Van Tichelen

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 231-241

Technical Paper / dx.doi.org/10.1080/00295450.2019.1637240

Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor

A. M. Tentner, A. Karahan, S. H. Kang

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 242-254

Technical Paper / dx.doi.org/10.1080/00295450.2019.1636589

Wall-Modeled Large Eddy Simulation of the Flow Through PWR Fuel Assemblies at ReH = 66 000—Validation on CALIFS Experimental Setup

Marie-Charlotte Gauffre, Sofiane Benhamadouche, Pierre-Bernard Badel

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 255-265

Technical Paper / dx.doi.org/10.1080/00295450.2019.1642684

Direct Numerical Simulation of Turbulent Flow Inside a Differentially Heated Composite Cavity

Javier Martínez, Elia Merzari, Michael Acton, Emilio Baglietto

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 266-282

Technical Paper / dx.doi.org/10.1080/00295450.2019.1595312

High-Performance Computing for Nuclear Reactor Design and Safety Applications

Afaque Shams, Dante De Santis, Adam Padee, Piotr Wasiuk, Tobiasz Jarosiewicz, Tomasz Kwiatkowski, Sławomir Potempski

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 283-295

Technical Paper / dx.doi.org/10.1080/00295450.2019.1642683

Numerical Simulation of Isothermal Flow Across Slant Five-Tube Bundle with Spectral Element Method Code Nek5000

Mustafa Alper Yildiz, Haomin Yuan, Elia Merzari, Yassin Hassan

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 296-306

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626176

Velocity and Scalar Fields of a Turbulent Buoyant Jet in the Self-Similar Region

Sunming Qin, Benedikt Krohn, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 307-321

Technical Paper / dx.doi.org/10.1080/00295450.2019.1591155

Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors

Nicholas R. Brown, David J. Diamond, Stephen Bajorek, Richard Denning

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 322-338

Technical Paper / dx.doi.org/10.1080/00295450.2019.1590077

Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux

Soon K. Lee, Maolong Liu, Nicholas R. Brown, Kurt A. Terrani, Youho Lee

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 339-346

Technical Paper / dx.doi.org/10.1080/00295450.2019.1670010

Interfacial Structures in Bubbly-to-Slug Transition Flows in a Duct

Guanyi Wang, Qingzi Zhu, Mamoru Ishii

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 347-357

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626175

Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces

Mingfu He, Youho Lee

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 358-374

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626177

Simulation of Boiling Two-Phase Flow in a Helical Coil Steam Generator Using the Spectral Element Code Nek-2P

Dillon R. Shaver, Nate Salpeter, Ananias Tomboulides, Prasad Vegendla, Adrian Tentner, W. David Pointer, Elia Merzari

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 375-387

Technical Paper / dx.doi.org/10.1080/00295450.2019.1664199

 
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