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Volume 164

Number 1 | Number 2 | Number 3

Number 1

Improved Reaction Rate Tracking and Fission Product Yield Determinations for the Monte Carlo-Linked Depletion Capability in MCNPX

Michael L. Fensin, John S. Hendricks, Samim Anghaie

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 3-12

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4003

Neptunium in the Fuel Cycle: Nonproliferation Benefits Versus Industrial Drawbacks

Selena Ng, Dominique Grenèche, Bernard Guesdon, Richard Vinoche, Marc Delpech, Florence Dolci, Hervé Golfier, Christine Poinot-Salanon

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 13-19

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4004

Coupled Neutronic and Thermal-Hydraulic Out-of-Phase Stability of Supercritical Water-Cooled Reactors

Jiyun Zhao, Pradip Saha, Mujid S. Kazimi

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 20-33

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4005

Dynamics of Molten Salt Reactors

Jiri Krepel, Ulrich Rohde, Ulrich Grundmann, Frank-Peter Weiss

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 34-44

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4006

Development of Analytical Procedures of Two-Phase Flow in Tight-Lattice Fuel Bundles for Innovative Water Reactor for Flexible Fuel Cycle

Hiroyuki Yoshida, Akira Ohnuki, Takeharu Misawa, Kazuyuki Takase, Hajime Akimoto

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 45-54

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4007

Validation of the CATHARE2 Code Against Oberhausen II Data

Fabrice Bentivoglio, Nicolas Tauveron

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 55-75

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4008

Large Eddy Simulation of Highly Fluctuational Temperature and Velocity Fields Observed in a Mixing-Tee Experiment

Pierre Coste, Patrick Quemere, Pierre Roubin, Philippe Emonot, Masaaki Tanaka, Hideki Kamide

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 76-88

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4009

Heat Transfer for Subcooled Flow Boiling in Hypervapotron Configuration

Peipei Chen, Wen Wu, Barclay G. Jones, Ty A. Newell

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 89-96

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4010

Experimental Results of Pebble Bed Thermal-Hydraulic Characteristics

Sigitas Rimkevicius, Eugenijus Uspuras

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 97-102

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4011

Temperature and Flow Distributions in Sodium-Heated Large Straight Tube Steam Generator by Numerical Methods

Naoyuki Kisohara, Takeshi Moribe, Takaaki Sakai

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 103-118

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4012

Experimental Investigation on the Heat Transfer Characteristics in Upward Flow of Supercritical Carbon Dioxide

Hyungrae Kim, Yoon Yeong Bae, Hwan Yeol Kim, Jin Ho Song, Bong Hyun Cho

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 119-129

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4013

Compatibility of Selected Ni-Based Alloys in Molten Li,Na,Be/F Salts with PuF3 and Tellurium Additions

Victor Ignatiev, Aleksandr Surenkov, Ivan Gnidoi, Vladimir Fedulov, Vadim Uglov, Valery Afonichkin, Andrei Bovet, Vladimir Subbotin, Aleksandr Panov, Andrei Toropov

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 130-142

Technical Paper / Icapp '06 / dx.doi.org/10.13182/NT08-A4014

Assessment of Two-Phase Flow Heat Transfer Correlations for Molten Core-Concrete Interaction Study

B. Tourniaire, O. Varo

Nuclear Technology / Volume 164 / Number 1 / October 2008 / Pages 143-151

Technical Note / Icapp '06 / dx.doi.org/10.13182/NT164-143

Number 2

Numerical Modeling of the Gas Migration Test at the Grimsel Test Site (Switzerland)

Rainer Senger, Bill Lanyon, Paul Marschall, Stratis Vomvoris, Ai Fujiwara

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 155-168

Technical Paper / Tough206 / dx.doi.org/10.13182/NT08-A4016

Sensitivity Analysis for Joint Inversion of Ground-Penetrating Radar and Thermal-Hydrological Data from a Large-Scale Underground Heater Test

M. B. Kowalsky, J. Birkholzer, J. Peterson, S. Finsterle, S. Mukhopadhyay, Y. Tsang

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 169-179

Technical Paper / Tough206 / dx.doi.org/10.13182/NT08-A4017

Modeling Reactive Multiphase Flow and Transport of Concentrated Solutions

Guoxiang Zhang, Nicolas Spycher, Eric Sonnenthal, Carl Steefel, Tianfu Xu

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 180-195

Technical Paper / Tough206 / dx.doi.org/10.13182/NT08-A4018

Using TOUGHREACT to Model Laboratory Tests on the Interaction of NaNO3-NaOH Fluids with Sandstone Rock at a Deep Radionuclide Repository Site

A. V. Kiryukhin, E. P. Kaymin, E. V. Zakharova

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 196-206

Technical Paper / Tough206 / dx.doi.org/10.13182/NT08-A4019

Lessons Learned from Sodium-Cooled Fast Reactor Operation and Their Ramifications for Future Reactors with Respect to Enhanced Safety and Reliability

J. Guidez, L. Martin, S. C. Chetal, P. Chellapandi, Baldev Raj

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 207-220

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT08-A4020

An Enhanced Code for the Safety Analysis of Pool-Type Sodium-Cooled Fast Reactors

Kwi Seok Ha, Hae Yong Jeong, Young Min Kwon, Yong Bum Lee, Dohee Hahn, James E. Cahalan, Floyd E. Dunn

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 221-231

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A4021

Experimental Investigations on the ESBWR Stability Performance

C. P. Marcel, M. Rohde, T. H. J. J. Van der Hagen

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 232-244

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A4022

Radiolytic Oxidation of Ruthenium Oxide Deposits

C. Mun, L. Cantrel, C. Madic

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 245-254

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A4023

Spherical Fuel Element Concept for Small Reactor Design

Kenneth Geelhood, Dean Matson, David Senor, Chad Painter

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 255-264

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A4024

RELAP5 Analyses of Thermal-Hydraulic Behavior in Steam Generator U-Tubes During Reflux Condensation

Noritoshi Minami, Toshiaki Chikusa, Michio Murase

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 265-277

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A4025

Experimental Study and Model Development on the Moisture Effect for Nuclear Graphite Oxidation

Eung Soo Kim, Chang Ho Oh, Hee Cheon No

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 278-285

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A4026

Advanced Polymer Composites for the Fabrication of Spent Nuclear Fuel Disposal Containers

Hugues W. Bonin, Ian Miedema, Van Tam Bui

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 286-304

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A4027

Nondestructive Determination of Relative Plutonium Content in MOX Fuel Pins for Pressurized Heavy Water Reactors Using Passive Gamma Scanning

K. V. Vrinda Devi, T. Soreng, J. P. Panakkal, H. S. Kamath

Nuclear Technology / Volume 164 / Number 2 / November 2008 / Pages 305-308

Technical Note / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT08-A4028

Number 3

Technology Assessment of Boiling Water Reactor Steam Supply Acoustic Performance and Wet Steam Sound Speed

Arthur E. Ruggles

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 309-319

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT08-A4029

Optimized Core Design of a Supercritical Carbon Dioxide-Cooled Fast Reactor

Christopher S. Handwerk, Michael J. Driscoll, Pavel Hejzlar

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 320-336

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT08-A4030

Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup

Yang-Hyun Koo, Byung-Ho Lee, Jae-Yong Oh, Kun-Woo Song

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 337-347

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A4031

Nuclear Energy for a Low-Carbon-Dioxide-Emission Transportation System with Liquid Fuels

Charles W. Forsberg

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 348-367

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT164-348

Performance Evaluation of the Safety Analysis Codes for Subcooled Boiling in a Nuclear Reactor Downcomer During the Late Reflood Phase of an LBLOCA

D. J. Euh, B. G. Huh, B. J. Yun, C.-H. Song, I. G. Kim

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 368-384

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT164-368

Heat Transfer Issues Associated with a Hypothetical Failure of the MEGAPIE Spallation Source Target Window

Brian L. Smith, Sergey V. Shepel

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 385-409

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A4034

Technology Gap Analysis on Sodium-Heated Steam Generators Supporting Advanced Burner Reactor Development

Yoshitaka Chikazawa, Mitchell Farmer, Christopher Grandy

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 410-432

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT08-A4035

Electrochemical Reduction of MOX Pellets in Molten Lithium Chloride Based on a Practical Operating Condition

Masaki Kurata, Noboru Yahagi, Shinichi Kitawaki, Akira Nakayoshi, Mineo Fukushima

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 433-441

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT08-A4036

Radionuclide Transport in a Water-Saturated Planar Fracture with Bentonite Extrusion

R. A. Borrelli, Joonhong Ahn

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 442-464

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A4037

EBR-II Superheater Duplex Tube Examination

Daniel M. Wachs, Dennis D. Keiser, Douglas L. Porter, Naoyuki Kisohara

Nuclear Technology / Volume 164 / Number 3 / December 2008 / Pages 465-473

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A4038

 

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