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