ANS / Publications / Journals / Nuclear Technology

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