ANS / Publications / Journals / Nuclear Technology

A Second Generation Multiphase-CFD Framework Toward Predictive Modeling of DNB

Emilio Baglietto, Etienne Demarly, Ravikishore Kommajosyula, Nazar Lubchenko, Ben Magolan, Rosie Sugrue

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 1-22

Technical Paper / dx.doi.org/10.1080/00295450.2018.1517528

The Implementation of an Activated Temperature-Dependent Wall Boiling Model in an Eulerian-Eulerian Computational Fluid Dynamics Approach for Predicting the Wall Boiling Process

Wei Ding, Eckhard Krepper, Uwe Hampel

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 23-32

Technical Paper / dx.doi.org/10.1080/00295450.2018.1496693

High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors

E. Merzari, H. Yuan, A. Kraus, A. Obabko, P. Fischer, J. Solberg, S. Lee, J. Lai, M. Delgado, Y. Hassan

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 33-47

Technical Paper / dx.doi.org/10.1080/00295450.2018.1490124

A Multiscale Approach Simulating Boiling in a Heated Pipe Including Flow Pattern Transition

T. Höhne, E. Krepper, D. Lucas, G. Montoya

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 48-56

Technical Paper / dx.doi.org/10.1080/00295450.2018.1495025

CFD Modeling Development for DNB Prediction of Rod Bundle with Mixing Vanes Under PWR Conditions

Yiban Xu, Robert A. Brewster, Michael E. Conner, Zeses E. Karoutas, L. David Smith, III

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 57-67

Technical Paper / dx.doi.org/10.1080/00295450.2018.1510265

Study on the Lateral Velocity and Vortex in a Spacer Grid

Bin Han, Bao-Wen Yang, Cen Wei, Yudong Zha

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 68-76

Technical Paper / dx.doi.org/10.1080/00295450.2018.1506658

Multidimensional Hydraulic Solver Using Structured and Unstructured Meshes for the System Thermal-Hydraulic Code SPACE

Chan Eok Park, Jong Ho Choi, Gyu Cheon Lee, Sang Yong Lee

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 77-93

Technical Paper / dx.doi.org/10.1080/00295450.2018.1501990

Pressure and Velocity Fluctuation in the Numerical Simulation of Bubble Detachment in a Venturi-Type Bubble Generator

Kangbei Cai, Yuchen Song, Jingjing Li, Dezhong Wang, Junlian Yin, Wei Liu, Hua Li

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 94-103

Technical Paper / dx.doi.org/10.1080/00295450.2018.1479575

Energetic Liquid Droplet Boiling on High-Temperature Metal Surfaces

D. Moghul, J. C. Luxat

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 104-118

Technical Paper / dx.doi.org/10.1080/00295450.2018.1515411

Development of Unstructured Mesh-Based Numerical Method for Sodium-Water Reaction Phenomenon

A. Uchibori, A. Watanabe, T. Takata, H. Ohshima

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 119-127

Technical Paper / dx.doi.org/10.1080/00295450.2018.1499323

Uncertainty Analysis of the Conditional Exceedance Probability Calculation for a Probabilistically Significant SBO Sequence

Y. Du, H. X. Li, T. H. Liang, K. S. Liang

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 128-139

Technical Paper / dx.doi.org/10.1080/00295450.2018.1494998

Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications

Jinzhao Zhang, Adrien Dethioux, Andriy Kovtonyuk, Christophe Schneidesch

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 140-152

Technical Paper / dx.doi.org/10.1080/00295450.2018.1516055

Evaluation of the PAR Mitigation System in Swiss PWR Containment Using the GOTHIC Code

Davide Papini, Michele Andreani, Pascal Steiner, Bojan Ničeno, Jens-Uwe Klügel, Horst-Michael Prasser

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 153-173

Technical Paper / dx.doi.org/10.1080/00295450.2018.1505356

Sensitivity Analysis of LB-LOCA in Response to Proposed 10 CFR 50.46c New Rulemaking

Hongbin Zhang, Ronaldo Szilard, Ling Zou, Haihua Zhao

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 174-187

Technical Paper / dx.doi.org/10.1080/00295450.2018.1496694

Thermal-Hydraulic Analysis of the LBE Spallation Target Head in JAEA

T. Wan, H. Obayashi, T. Sasa

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 188-199

Technical Paper / dx.doi.org/10.1080/00295450.2018.1478591

Measurement of Type 304L Stainless Steel and 16MND5 Ferritic Steel Density and Surface Tension: Possible Impact for Stratified Molten Pool

N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 200-212

Technical Paper / dx.doi.org/10.1080/00295450.2018.1486160

High-Resolution Velocity Field Measurements of Turbulent Round Free Jets in Uniform Environments

Sunming Qin, Benedikt Krohn, John Downing, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 213-225

Technical Paper / dx.doi.org/10.1080/00295450.2018.1470864

Effects of Substrate Materials and Surface Conditions on the Minimum Film-Boiling Temperature

Shikha A. Ebrahim, Ece Alat, Faruk A. Sohag, Valerie Fudurich, Shi Chang, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 226-238

Technical Paper / dx.doi.org/10.1080/00295450.2018.1490122

Corium-Sodium and Corium-Water Fuel-Coolant-Interaction Experimental Programs for the PLINIUS2 Prototypic Corium Platform

Christophe Journeau, Laurence Aufore, Léonie Berge, Claude Brayer, Nathalie Cassiaut-Louis, Nicolas Estre, Frédéric Payot, Pascal Piluso, Jean-Christophe Prele, Shifali Singh, Magali Zabiégo, Eric Pluyette, Frédéric Serre, Béatrice Teisseire

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 239-247

Technical Paper / dx.doi.org/10.1080/00295450.2018.1479580

Multiscaled Experimental Investigations of Corrosion and Precipitation Processes After Loss-of-Coolant Accidents in Pressurized Water Reactors

Stefan Renger, Sören Alt, Ulrike Gocht, Wolfgang Kästner, André Seeliger, Holger Kryk, Ulrich Harm

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 248-261

Technical Paper / dx.doi.org/10.1080/00295450.2018.1499324

Development and Application of Molecular Tagging Velocimetry for Gas Flows in Thermal Hydraulics

Matthieu A. André, Ross A. Burns, Paul M. Danehy, Seth R. Cadell, Brian G. Woods, Philippe M. Bardet

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 262-271

Technical Paper / dx.doi.org/10.1080/00295450.2018.1516954

Simultaneous PIV/PLIF and Pulsed Shadowgraphy Measurement of Gas-Liquid Flows in a Swirling Separator

Yalan Qian, Tingting Zhang, Jingjing Li, Yuchen Song, Junlian Yin, Dezhong Wang, Hua Li, Wei Liu

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 272-280

Technical Paper / dx.doi.org/10.1080/00295450.2018.1486161

Study of Bottom Reflooding in a Narrow Rectangular Channel

Wei Xu, Jianhua Xia, Xiaojing Liu, Xu Cheng, Wei Zeng

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 281-296

Technical Paper / dx.doi.org/10.1080/00295450.2018.1457887

Experimental Study of Blowdown Event in a PWR-Type Small Modular Reactor

Guanyi Wang, Yikuan Yan, Shanbin Shi, Zhuoran Dang, Xiaohong Yang, Mamoru Ishii

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 297-306

Technical Paper / dx.doi.org/10.1080/00295450.2018.1493317

Rod Bundle Heat Transfer Thermal-Hydraulic Program

Stephen M. Bajorek, Fan-Bill Cheung

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 307-327

Technical Paper / dx.doi.org/10.1080/00295450.2018.1510697

The Impact of Mixing Vane Arrangement on Mixing Coefficient β for Subchannel Analysis

Cen Wei, Bao-Wen Yang, Bin Han, Aiguo Liu

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 328-337

Technical Paper / dx.doi.org/10.1080/00295450.2018.1510266

Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows

Xingang Zhao, Aaron J. Wysocki, Koroush Shirvan, Robert K. Salko

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 338-351

Technical Paper / dx.doi.org/10.1080/00295450.2018.1507221

Application of the Improved Spacer Grid Model in Subchannel Analysis Code

Siying Dong, Wei Liu, Yang Liu, Jianqiang Shan

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 352-363

Technical Paper / dx.doi.org/10.1080/00295450.2018.1491182

Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water

Pan Wu, David Novog

Nuclear Technology / Volume 205 / Number 1-2 / January-February 2019 / Pages 364-376

Technical Paper / dx.doi.org/10.1080/00295450.2018.1495000