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

Methodology for Designing a Sodium-Cooled Fast Reactor with Inherent Safety

N. E. Stauff, L. Buiron, B. Fontaine, G. Rimpault

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 241-250

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A15781

Superprism-Sized Breed-and-Burn Sodium-Cooled Core Performance

Florent Heidet, Ehud Greenspan

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 251-273

Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15782

Shape Optimization of an Outlet Plenum of a Pebble Bed Modular Reactor

Jae-Woo Ju, Sang-Moon Lee, Kwang-Yong Kim

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 274-281

Technical Paper / Fission Reactors/Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15783

Critical Mass Estimates for Homogeneous Metal-Water Mixtures of Key Fissionable Nuclides

Drew E. Kornreich

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 282-302

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-A15784

New Risk Assessment Method for a Reprocessing Plant: Quantitative Safety Assessment

Yoshikazu Tamauchi, Takashi Miyata, Kazumi Takebe, Yoshiaki Hayashi, Shingo Matsuoka, Kazuya Hayashi, Katsuya Kurosu

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 303-316

Technical Paper / Reactor Safety/Reprocessing / dx.doi.org/10.13182/NT13-A15785

Fuel Cycle Investigation for Wallpaper-Type HTR Fuel

Alain Marmier, Michael A. Fütterer, Kamil Tucek, Jim C. Kuijper, Jaap Oppe, Biser Petrov, Jérôme Jonnet, Jan Leen Kloosterman, Brian Boer

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 317-330

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15786

Synthesis Route for the Safe Production of Targets for Transmutation of Plutonium and Minor Actinides

Catharina Nästrén, Asunción Fernandéz-Carretero, Joseph Somers

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 331-336

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15787

Investigation of Fission Product Transport into Zeolite-A for Pyroprocessing Waste Minimization

James R. Allensworth, Michael F. Simpson, Man-Sung Yim, Supathorn Phongikaroon

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 337-348

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-A15788

Photon Intermediate Direct Energy Conversion Using a ⁹⁰Sr Beta Source

Robert J. Schott, Charles L. Weaver, Mark A. Prelas, Kyuhak Oh, Jason B. Rothenberger, R. V. Tompson, Denis A. Wisniewski

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 349-353

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT13-A15789

Development of Self-Interrogation Neutron Resonance Densitometry to Improve Detection of Possible Diversions for PWR Spent Fuel Assemblies

Adrienne M. Lafleur, William S. Charlton, Howard O. Menlove, Martyn T. Swinhoe, Alain R. Lebrun

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 354-370

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT13-A15790

Synthesis of Silica-Coated Uranium Oxide Nanoparticles by Surfactant-Templated Sol-Gel Process for Use as Catalysts

Shameem Hasan, Tushar K. Ghosh

Nuclear Technology / Volume 181 / Number 2 / February 2013 / Pages 371-379

Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT13-A15791

Performance of Large Breed-and-Burn Core

Florent Heidet, Ehud Greenspan

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 381-407

Technical Papers / Fission Reactors / dx.doi.org/10.13182/NT13-A15800

Performance Assessment for Geological Disposal of Graphite Waste Containing TRISO Particles

Bret Patrick van den Akker, Joonhong Ahn

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 408-426

Technical Papers / Fission Reactors/Fuel Cycle and Management/Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-103

Fuel Cycle System Analysis Implications of Sodium-Cooled Metal-Fueled Fast Reactor Transuranic Conversion Ratio

Steven J. Piet, Edward A. Hoffman, Samuel E. Bays, Gretchen E. Matthern, Jacob J. Jacobson, Ryan Clement, David W. Gerts

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 427-458

Technical Papers / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15802

Artificial Neural Network Modeling of In-Reactor Axial Elongation of Zr2.5%Nb Pressure Tubes at RAPS 4 PHWR

A. Sarkar, S. K. Sinha, J. K. Chakravartty, R. K. Sinha

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 459-465

Technical Papers / Fuel Cycle and Management/Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-A15803

Large-Eddy Simulation of Turbulent Flow with Heat Transfer in a Rod Bundle

Constantine P. Tzanos, Maxim Popov

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 466-478

Technical Papers / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A15804

Experimental Investigation into the Effect of the Passive Condensation Cooling Tank Water Level in the Thermal Performance of the Passive Auxiliary Feedwater System

Byoung-Uhn Bae, Seok Kim, Yu-Sun Park, Kyoung-Ho Kang, Byong-Jo Yun

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 479-492

Technical Papers / Thermal Hydraulics / dx.doi.org/10.13182/NT181-479

Robust Nonlinear Method for Steam Generator Level Control

Ahmad Osgouee, Jin Jiang

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 493-506

Technical Papers / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-A15806

Development of Treatment Process for Anode Residue from Molten Salt Electrorefining of Spent Metallic Fast Reactor Fuel

Masatoshi Iizuka, Masaaki Akagi, Takashi Omori

Nuclear Technology / Volume 181 / Number 3 / March 2013 / Pages 507-525

Technical Papers / Reprocessing / dx.doi.org/10.13182/NT13-A15807