ANS / Publications / Journals / Nuclear Technology

Risk-Informed Design Changes in a Passive Decay Heat Removal System

Giovanbattista Patalano, George E. Apostolakis, Pavel Hejzlar

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 191-208

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3981

Validation of Severe Accident Codes on the Phebus Fission Product Tests in the Framework of the PHEBEN-2 Project

K. Mueller, S. Dickinson, C. de Pascale, N. Girault, L. Herranz, F. De Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuertes, I. Turcu, I. Ivanov, B. Toth, G. Horvath

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 209-227

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3982

Aerosol Studies in a Nuclear Aerosol Test Facility Under Different Turbulence Conditions

B. K. Sapra, Y. S. Mayya, Arshad Khan, Faby Sunny, Sunil Ganju, H. S. Kushwaha

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 228-244

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3983

Quantum-Chemical Calculations of the Equilibrium Constants of a Fission Product Mixture in a Steam-Hydrogen Carrier Gas in Severe Accident Conditions

Jan Machacek, Laurent Cantrel, Peter Kluvanek, Marek Liska, Ondrej Gedeon

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 245-251

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3984

Behavior of a Defective Nuclear Fuel Rod in Dry Storage Conditions Studied with a New Experimental Setup

L. Desgranges, M. P. Ferroud-Plattet, R. Alloncle, I. Aubrun, J. M. Untrau, P. Lhuillery

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 252-260

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3985

Analysis of Steam Condensation Heat Transfer with a Noncondensable Gas in a Vertical Condenser Tube

Kwon-Yeong Lee, Moo Hwan Kim

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 261-272

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3986

COBRA-TF Analysis of the High Flux Reactor Hot Channel for a Postulated Large-Break Loss-of-Coolant Accident

Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 273-284

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3987

Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - I: Two-Layer System Mass Transfer Theory

Michael Epstein, Hans K. Fauske, Charles F. Askonas, Marc A. Vial, Patricia Paviet-Hartmann

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 285-293

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT08-A3988

Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - II: Experimental Data on Reaction Self-Heat Rates and Gas Production and Their Correlation

Michael Epstein, Hans K. Fauske, Charles F. Askonas, Marc A. Vial, Patricia Paviet-Hartmann

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 294-306

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT08-A3989

Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - III: Predictions of Thermal Stability Boundaries and Required Vent Size

Michael Epstein, Hans K. Fauske, Charles F. Askonas, Marc A. Vial, Patricia Paviet-Hartmann

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 307-320

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT08-A3990

Production of High-Density Uranium Carbide Compacts for Use in Composite Nuclear Fuels

Gokul Vasudevamurthy, Travis W. Knight

Nuclear Technology / Volume 163 / Number 2 / August 2008 / Pages 321-327

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A3991