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Number 1

Table of Contents
Foreword: NURETH-12 Special Issue (Fan-Bill Cheung, Karen Vierow, Joy Rempe)

Geometric Effects of 45-deg Elbow in Horizontal Air-Water Bubbly Flow
Justin D. Talley, Seungjin Kim, Tangwen Guo, Gunol Kojasoy
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 2-12
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT167-2
Variable Property Effects on Vapor Condensation with a Noncondensable Gas
Yehong Liao, Karen Vierow
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 13-19
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT167-13
Interfacial Area Transport in Horizontal Bubbly Flow with 90-deg Elbow
Seungjin Kim, Kennard Callender, Gunol Kojasoy
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 20-28
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8848
On the Computation of Multiphase Flows
Richard T. Lahey, Jr.
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 29-45
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT167-29
CFD Modeling and Experiments of Insulation Debris Transport Phenomena in Water Flow
Eckhard Krepper, Gregory Cartland-Glover, Alexander Grahn, Frank-Peter Weiss, Sören Alt, Rainer Hampel, Wolfgang Kästner, André Seeliger
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 46-59
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8850
Validation of NEPTUNE_CFD Module with Data of a Plunging Water Jet Entering a Free Surface
M. C. Galassi, D. Bestion, C. Morel, J. Pouvreau, F. D'Auria
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 60-70
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8851
CFD Simulation of Phase Distribution in Adiabatic Upward Bubbly Flows Using Interfacial Area Transport Equation
Xia Wang, Xiaodong Sun
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 71-82
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8852
Numerical Analysis of Melting/Solidification Phenomena Using a Moving Boundary Analysis Method X-FEM
A. Uchibori, H. Ohshima
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 83-94
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8853
Simulation of Sulfur-Iodine Thermochemical Hydrogen Production Plant Coupled to High-Temperature Heat Source
Nicholas R. Brown, Seungmin Oh, Shripad T. Revankar, Karen Vierow, Salvador Rodriguez, Randall Cole, Jr., Randall Gauntt
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 95-106
Technical Paper | NURETH-12 / Fuel Cycle and Management | doi.org/10.13182/NT09-A8854
RCCS Experiments and Validation for High-Temperature Gas-Cooled Reactor
Chang H. Oh, Goon C. Park, Cliff Davis
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 107-117
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8855
Thermal Influence on Steam Generator Heat Transfer Tube During Sodium-Water Reaction Accident of Sodium-Cooled Fast Reactor
Akira Yamaguchi, Takashi Takata, Hiroyuki Ohshima, Akikazu Kurihara
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 118-126
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8856
Thermal-Hydraulic Challenges in Fast Reactor Design
Neil E. Todreas
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 127-144
Technical Paper | NURETH-12 / Fission Reactors | doi.org/10.13182/NT09-A8857
Transport Phenomena in Supercritical Fluids in Gen-IV Reactor Designs
Michael L. Corradini
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 145-156
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8858
Assessment of Steam Generator Tube Flaw Size and Leak Rate Models
Shripad T. Revankar, Jovica R. Riznic
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 157-168
Technical Paper | NURETH-12 / Nuclear Plant Operations and Control | doi.org/10.13182/NT09-A8859
Options Extending the Applicability of High-Temperature Irradiation-Resistant Thermocouples
Joy L. Rempe, Darrell L. Knudson, Keith G. Condie, John C. Crepeau, Joshua E. Daw, S. Curtis Wilkins
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 169-177
Technical Paper | NURETH-12 / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-14
Optimal Gap Size for Downward Facing Boiling and Steam Venting in a Hemispherical Annular Channel
Shankar Narayanan, Fan-Bill Cheung, Lawrence Hochreiter
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 178-186
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8861
Thermal-Hydraulic Aspects of Progression to Severe Accidents in CANDU Reactors
John C. Luxat
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 187-210
Technical Paper | NURETH-12 / Reactor Safety | doi.org/10.13182/NT09-A8862
Experimental Study on the Boiling Heat Removal at the Upper Surface of the Metallic Layer During Late-Phase Coolant Injection
Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Seong-Wan Hong
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 211-222
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8863
Dynamics and Preconditioning in a Single-Droplet Vapor Explosion
Roberta Concilio Hansson, Hyun Sun Park, Truc-Nam Dinh
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 223-234
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8864
Improvement of Core Modeling in ICARE/CATHARE: Application to the Calculation of a Six-Inch-Break LOCA Leading to a Severely Degraded Situation
Patrick Drai, Olivier Marchand, Patrick Chatelard, Florian Fichot, Joëlle Fleurot
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 235-246
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8865

Number 2

Table of Contents

Simplification of the Severe Accident Management Guideline for the Containment Flooding in a Mark-III Containment
Min-Jie Chuang, Shih-Jen Wang, Sheng-Yuan Fann, Show-Chyuan Chiang
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 247-253
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A8961
Feasibility Study on an Upgraded Future Monju Core Concept with Extended Operation Cycle Length of One Year and Increased Fuel Burnup
Hidehito Kinjo, Takeshi Kageyama, Akihiro Kitano, Shin Usami
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 254-267
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A8962
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Georgeta Radulescu, Donald E. Mueller, John C. Wagner
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 268-287
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT09-A8963
Analysis of a Generic Liquid-Metal Leak
K. Samec, R. Z. Milenkovic
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 288-303
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A8964
Analysis of Leaks Through Microchannel Cracks Using RELAP5-3D
Angelo Frisani, Yassin A. Hassan
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 304-312
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A8965
Use of Geometrically Accurate Fuel Models to Predict Cladding and Basket Temperatures Within a Truck Cask During Normal Transport
Venkata V. R. Venigalla, Miles Greiner
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 313-324
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A8966
Dimensionless Numbers in Phase-Change Thermosyphon and Heat-Pipe Heat Exchangers
Piyush Sabharwall, Vivek Utgikar, Fred Gunnerson
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 325-332
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT09-A8967
Extraction of U(VI) by Tri-n-Amyl Phosphate Under High Solvent Loading Conditions
A. Suresh, N. L. Sreenivasan, Robert Selvan, M. P. Antony, T. G. Srinivasan, S. B. Koganti, P. R. Vasudeva Rao
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 333-338
Technical Note | Reprocessing | doi.org/10.13182/NT09-A8968

Number 3

Table of Contents
Book Review (Nicholas Tsoulfanidis)

Hazard Assessment of the CIRCE Lead-Bismuth Experimental Facility in the ICE Configuration
Luciano Burgazzi
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 339-347
Technical Paper | Reactor Safety | doi.org/10.13182/NT09-A9074
Feasibility Study on a Simplified MOX Pellet Fabrication Process, the Short Process, for Fast Breeder Reactor Fuel
Koichi Asakura, Kentaro Takeuchi, Takayoshi Makino, Yoshiyuki Kato
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 348-361
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT09-A9075
Use of Isotopically Modified Erbium in Advanced LWR Fuel
Fausto Franceschini, Bojan Petrovic
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 362-370
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT09-A9076
Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Arrays of Heated Rods
N. R. Chalasani, Pablo E. Araya, Miles Greiner
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 371-383
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT167-371
Benchmark of Natural Convection/Radiation Simulations Within an Enclosed Array of Horizontal Heated Rods
Pablo E. Araya, Miles Greiner
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 384-394
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A9078
Calculation of Photon Exposure and Ambient Dose Slant-Path Buildup Factors for Radiological Assessment
Fritz G. Schirmers, Adam Davis, H. Omar Wooten, Donald J. Dudziak, Man-Sung Yim, David McNelis
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 395-409
Technical Paper | Radiation Protection | doi.org/10.13182/NT09-1
Ammonium Polyuranate Precipitation from Fluoride Solutions: An Experimental Study of the UO₃-HF-NH₃-H₂O System as Applied in UF₆ Processing
A. B. Rothman, D. G. Graczyk
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 410-420
Technical Paper | Reprocessing | doi.org/10.13182/NT09-A9080

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