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Volume 167 / Number 1

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Nuclear Technology / Volume 167 / Number 1

July 2009

Foreword: NURETH-12 Special Issue

Fan-Bill Cheung, Karen Vierow, Joy Rempe

Nuclear Technology / Volume 167 / Number 1 / Page 1

July 2009

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 / Pages 2-12

July 2009

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Variable Property Effects on Vapor Condensation with a Noncondensable Gas

Yehong Liao, Karen Vierow

Nuclear Technology / Volume 167 / Number 1 / Pages 13-19

July 2009

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Interfacial Area Transport in Horizontal Bubbly Flow with 90-deg Elbow

Seungjin Kim, Kennard Callender, Gunol Kojasoy

Nuclear Technology / Volume 167 / Number 1 / Pages 20-28

July 2009

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On the Computation of Multiphase Flows

Richard T. Lahey, Jr.

Nuclear Technology / Volume 167 / Number 1 / Pages 29-45

July 2009

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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 / Pages 46-59

July 2009

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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 / Pages 60-70

July 2009

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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 / Pages 71-82

July 2009

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Numerical Analysis of Melting/Solidification Phenomena Using a Moving Boundary Analysis Method X-FEM

A. Uchibori, H. Ohshima

Nuclear Technology / Volume 167 / Number 1 / Pages 83-94

July 2009

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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 / Pages 95-106

July 2009

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RCCS Experiments and Validation for High-Temperature Gas-Cooled Reactor

Chang H. Oh, Goon C. Park, Cliff Davis

Nuclear Technology / Volume 167 / Number 1 / Pages 107-117

July 2009

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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 / Pages 118-126

July 2009

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Thermal-Hydraulic Challenges in Fast Reactor Design

Neil E. Todreas

Nuclear Technology / Volume 167 / Number 1 / Pages 127-144

July 2009

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Transport Phenomena in Supercritical Fluids in Gen-IV Reactor Designs

Michael L. Corradini

Nuclear Technology / Volume 167 / Number 1 / Pages 145-156

July 2009

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Assessment of Steam Generator Tube Flaw Size and Leak Rate Models

Shripad T. Revankar, Jovica R. Riznic

Nuclear Technology / Volume 167 / Number 1 / Pages 157-168

July 2009

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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 / Pages 169-177

July 2009

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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 / Pages 178-186

July 2009

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Thermal-Hydraulic Aspects of Progression to Severe Accidents in CANDU Reactors

John C. Luxat

Nuclear Technology / Volume 167 / Number 1 / Pages 187-210

July 2009

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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 / Pages 211-222

July 2009

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