ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT09-A8865

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT09-A8968

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT09-A9080