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Number 1

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT13-A15770

Number 2

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT13-A15791

Number 3

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT13-A15807

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