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Volume 206

Number 1 | Number 2

Number 1

A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties

Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 1-22

Critical Review / dx.doi.org/10.1080/00295450.2019.1623617

Pyrolytic Carbon Coating Effects on Oxide and Carbide Kernels Intended for Nuclear Fuel Applications

Miles F. Beaux, II, Douglas R. Vodnik, Reuben J. Peterson, Bryan L. Bennett, Kevin M. Hubbard, Brian M. Patterson, Jeffrey D. Goettee, James D. Jurney, Graham M. King, Alice I. Smith, Eric L. Tegtmeier, Erik P. Luther, Venkateswara R. Dasari, (DV Rao), David J. Devlin, Igor O. Usov

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 23-31

Technical Paper / dx.doi.org/10.1080/00295450.2019.1618683

Displacement Cascades in Monocrystalline Silicon: Effects of Temperature, Strain, and PKA Energy

Yuan Zhou, Bing Chen, Hongyu He, Bo Li, Xinlin Wang

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 32-39

Technical Paper / dx.doi.org/10.1080/00295450.2019.1613850

Rapid Clogging of High-Efficiency Particulate Air Filters During In-Cell Solvent Fires at Reprocessing Facilities

Takuya Ohno, Shinsuke Tashiro, Yuki Amano, Ryoichiro Yoshida, Hitoshi Abe

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 40-47

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620057

Fuel Cycle Analysis of Novel Assembly Design for Thorium-Uranium-Ceramic–Fueled Thermal, High-Conversion Reactor

N. Kaffezakis, D. Kotlyar

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 48-72

Technical Paper / dx.doi.org/10.1080/00295450.2019.1616475

A Method to Estimate Fission Product Concentration Uncertainty in a Multi-Time-Step MCNP6 Code Nuclear Fuel Burnup Calculation

Yasuhiro Minamigawa, Evans D. Kitcher, Sunil S. Chirayath

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 73-81

Technical Paper / dx.doi.org/10.1080/00295450.2019.1624429

Effectiveness of Model-Based Defenses for Digitally Controlled Industrial Systems: Nuclear Reactor Case Study

Yeni Li, Elisa Bertino, Hany S. Abdel-Khalik

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 82-93

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626170

Using Artificial Neural Networks for Predicting Mental Workload in Nuclear Power Plants Based on Eye Tracking

Yiqian Wu, Zhiyao Liu, Ming Jia, Cong Chi Tran, Shengyuan Yan

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 94-106

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620055

Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems

Douglas E. Peplow, Kaushik Banerjee, Gregory G. Davidson, Ian R. Stewart, Mathew W. Swinney, Jackson N. Wagner

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 107-125

Technical Paper / dx.doi.org/10.1080/00295450.2019.1625663

Investigative Study of Neutronic Safety Parameters of HPR and EPR Using the MCNP Code

R G. Abrefah, P. M. Atsu, R. B. M. Sogbadji

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 126-132

Technical Note / dx.doi.org/10.1080/00295450.2019.1618130

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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