ANS / Publications / Journals / Nuclear Technology

Supercritical Flow and Heat Transfer: Experiments and Analyses

M. Corradini

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 2-10

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15752

Thermal Hydraulics of Sodium-Cooled Fast Reactors: Key Design and Safety Issues and Highlights

Hisashi Ninokata, Hideki Kamide

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 11-23

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15753

Korean Development of Advanced Thermal-Hydraulic Codes for Water Reactors and HTGRs: Space and Gamma

Hee Cheon No, Sang Jun Ha, Kyung Doo Kim, Hong Sik Lim, Eo Hwak Lee, Hyung Gon Jin

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 24-43

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15754

Coupled DNS/RANS Simulation of Fission Gas Discharge During Loss-of-Flow Accident in Generation IV Sodium Fast Reactor

F. Behafarid, D. Shaver, I. A. Bolotnov, S. P. Antal, K. E. Jansen, M. Z. Podowski

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 44-55

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Reactor Safety; Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15755

Challenges Associated with the Mitigation of Unprotected Loss of Flow in Sodium-Cooled Fast Reactor Cores

Gerald Rimpault, Sandra Poumerouly, Johann Lecerf

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 56-67

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics; Fission Reactors; Reactor Safety / dx.doi.org/10.13182/NT13-A15756

Isothermal Air-Ingress Validation Experiments

Chang H. Oh, Eung Soo Kim

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 68-80

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15757

Derivation of the Basic Equations and Simplified Transport Models of the Interfacial Area in Gas-Liquid Two-Phase Flow

Isao Kataoka, Kenji Yoshida, Masanori Naitoh, Hidetoshi Okada, Tadashi Morii

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 81-93

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15758

Effects of 90-deg Vertical Elbows on the Distribution of Local Two-Phase Flow Parameters

Mohan S. Yadav, Seungjin Kim

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 94-105

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15759

A Mechanistic Model for Droplet Deposition Heat Transfer in Dispersed Flow Film Boiling

Michael J. Meholic, David L. Aumiller, Jr., Fan-Bill Cheung

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 106-114

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT12-10

Experimental and Computational Analysis of Steam Condensation in the Presence of Air and Helium

Matteo Bucci, Walter Ambrosini, Nicola Forgione

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 115-132

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15761

Eulerian Simulation of Interacting PWR Sprays Including Droplet Collisions

A. Foissac, J. Malet, S. Mimouni, P. Ruyer, F. Feuillebois, O. Simonin

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 133-143

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15762

Algebraic Turbulent Heat Flux Model for Prediction of Thermal Stratification in Piping Systems

M. Pellegrini, H. Endo, E. Merzari, H. Ninokata

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 144-156

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15763

Developments Toward Mechanistic Modeling of Critical Heat Flux on a CANDU Calandria Tube Following Pressure Tube Contact

Azin Behdadi, John C. Luxat

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 157-169

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Reactor Safety; Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15764

A BEPU Analysis Separating Epistemic and Aleatory Errors to Compute Accurate Dryout Power Uncertainties

D. Pun-Quach, P. Sermer, F. M. Hoppe, O. Nainer, B. Phan

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 170-183

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Reactor Safety / dx.doi.org/10.13182/NT13-A15765

Extended Forward Sensitivity Analysis for Uncertainty Quantification

Haihua Zhao, Vincent A. Mousseau

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 184-195

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15766

Prediction of Boiling-Induced Natural-Circulation Flow in Engineered Cooling Channels

Kwang Soon Ha, Fan-Bill Cheung, Jinho Song, Rae Joon Park, Sang Baik Kim

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 196-207

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15767

Quenching Experiments: Coolability of Debris Bed

M. Rashid, S. Rahman, R. Kulenovic, M. Bürger, E. Laurien

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 208-215

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15768

LIVE-L4 and LIVE-L5L Experiments on Melt Pool and Crust Behavior in Lower Head of Reactor Pressure Vessel

X. Gaus-Liu, A. Miassoedov, J. Foit, T. Cron, F. Kretzschmar, Alexander Palagin, T. Wenz, S. Schmidt-Stiefel

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 216-226

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Reactor Safety / dx.doi.org/10.13182/NT13-A15769

Three-Dimensional Modeling of Debris Mixing and Sedimentation in Severe Accidents Using the Moving Particle Semi-Implicit Method Coupled with Rigid Body Dynamics

Shane Park, Hyun Sun Park, Gyoodong Jeun, Bum Jin Cho

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 227-239

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15770