ANS / Publications / Journals / Nuclear Technology

A Probabilistic Methodology to Determine Failure Probabilities and Acceptance Criteria for the KBS-3 Inserts Under Ice-Age Load Conditions

Karl-Fredrik Nilsson, Peter Dillström, Claes-Göran Andersson, Fred Nilsson, Mats Andersson, Philip Minnebo, Lars-Erik Bjorkegren, Bo Erixon

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 3-14

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3964

Factors Affecting Risk Predictions: Can Some Risk Metrics Be More Accurately Predicted Than Others?

Robert W. Rice, John C. Walton

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 15-23

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3965

Assessing Effects of Thermal Loading on the Stability of Emplacement Drifts

G. I. Ofoegbu, K. J. Smart, B. Dasgupta

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 24-30

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3966

An Analysis of External Radiation Dose Fields in an Underground Facility at the Potential HLW Geologic Repository at Yucca Mountain, Nevada

Oleg G. Povetko

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 31-37

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3967

Double-Diffusive Natural Convection in a Nuclear Waste Repository

Yue Hao, John J. Nitao, Thomas A. Buscheck, Yunwei Sun

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 38-46

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3968

Increased Storage Capacity at Yucca Mountain Favors Thermal Management for a Cold Repository

G. Danko, J. Walton, D. Bahrami

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 47-61

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3969

Modeling Temperature Distribution Around Very Deep Borehole Disposals of HLW

Fergus G. F. Gibb, Karl P. Travis, Neil A. McTaggart, David Burley, Kevin W. Hesketh

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 62-73

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3970

Impact of Advanced Fuel Cycles on Geological Disposal in a Clay Formation

Jan Marivoet, Eef Weetjens

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 74-84

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3971

Independent Evaluation of Waste Package Corrosion Performance Under Potential Repository Conditions

Y.-M. Pan, K. T. Chiang, D. S. Dunn, X. He, O. Pensado, P. Shukla, L. Yang

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 85-91

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3972

Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain

S. David Sevougian, Vivek Jain, Robert J. MacKinnon, Patrick D. Mattie, Kevin G. Mon, Bryan E. Bullard

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 92-100

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3973

Results from an International Simulation Study on Coupled Thermal, Hydrological, and Mechanical Processes near Geological Nuclear Waste Repositories

J. Rutqvist, D. Barr, J. T. Birkholzer, M. Chijimatsu, O. Kolditz, Quansheng Liu, Y. Oda, Wenqing Wang, Chengyuan Zhang

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 101-109

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3974

Coupled In-Rock and In-Drift Hydrothermal Model Study for Yucca Mountain

G. Danko, J. Birkholzer, D. Bahrami

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 110-128

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3975

Time-Domain Random-Walk Algorithms for Simulating Radionuclide Transport in Fractured Porous Rock

Scott L. Painter, Vladimir Cvetkovic, Osvaldo Pensado

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 129-136

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3976

Formulation of Time-Domain Random-Walk Compartment Model for Radionuclide Migration from a Geologic Repository

Daisuke Kawasaki, Joonhong Ahn

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 137-146

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3977

A Modeling Study Evaluating the Thermal-Hydrological Conditions in and near Waste Emplacement Drifts at Yucca Mountain

J. T. Birkholzer, N. Halecky, S. W. Webb, P. F. Peterson, G. S. Bodvarsson

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 147-164

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3978

Impact of Landscape Topography and Quaternary Overburden on the Performance of a Geological Repository of Nuclear Waste

Lars Marklund, Anders Wörman, Joel Geier, Eva Simic, Björn Dverstorp

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 165-179

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3979

Probabilistic Methodology for Long-Term Assessment of Volcanic Hazards

Olivier Jaquet, Charles Connor, Laura Connor

Nuclear Technology / Volume 163 / Number 1 / July 2008 / Pages 180-189

Technical Paper / High-Level Radioactive Waste Management / dx.doi.org/10.13182/NT08-A3980

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

Evaluation of Salt Coolants for Reactor Applications

D. F. Williams, K. T. Clarno

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 330-343

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT08-A3992

Options for Scaled Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Convective Heat Transfer

Philippe M. Bardet, Per F. Peterson

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 344-357

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT163-344

Influence of the Processing and Salt Composition on the Thorium Molten Salt Reactor

Elsa Merle-Lucotte, Ludovic Mathieu, Daniel Heuer, Véronique Ghetta, Roger Brissot, Christian Le Brun, Eric Liatard

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 358-365

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT08-A3994

Electrodeposition of Uranium and Transuranics Metals (Pu) on Solid Cathode

A. F. Laplace, J. Lacquement, J. L. Willit, R. A. Finch, G. A. Fletcher, M. A. Williamson

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 366-372

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT08-A3995

Electrochemical Determination of Gadolinium and Plutonium Solvation Properties in Liquid Gallium at High Temperature

Sylvie Delpech, Gérard Picard, Jörgen Finne, Eric Walle, Olivier Conocar, Annabelle Laplace, Jérôme Lacquement

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 373-381

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT08-A3996

A New Technology for the Nuclear Industry for the Complete and Continuous Pyrochemical Reprocessing of Spent Nuclear Fuel: Catalyst Enhanced Molten Salt Oxidation

Trevor R. Griffiths, Vladimir A. Volkovich

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 382-400

Technical Paper / Molten Salt Chemistry and Technology / dx.doi.org/10.13182/NT08-A3997

A Study of Air Ingress and Its Prevention in HTGR

Xing L. Yan, Tetsuaki Takeda, Tetsuo Nishihara, Kazutaka Ohashi, Kazuhiko Kunitomi, Nobumasa Tsuji

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 401-415

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT08-A3998

Finite Element Modeling of Thermal-Mechanical Behaviors of Dispersion Fuel Elements

Shurong Ding, Yongzhong Huo

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 416-425

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3999

A Comparison of Experimental Results and FLUENT Simulations for Void-Fraction Distribution in a Two-Phase System

R. Saksena, P. Satyamurthy, P. Munshi

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 426-434

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A4000

An Advanced Boiling Water Reactor Monitoring System Using Modular Accident Analysis Program and Computer Graphical User Interface

Yuan-Hsiang Chang, Mu-Ping Xu, Jyh-Tong Teng, Te-Chuan Wang, Ray-Feng Chiang, Huey-Ling Hwu, Wang-Chyuan Chen

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 435-443

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT08-A4001

A Novel Approach to Spent Fuel Pool Decommissioning

R. L. Demmer, J. B. Panozzo, R. J. Christensen

Nuclear Technology / Volume 163 / Number 3 / September 2008 / Pages 444-452

Technical Paper / Decontamination/decommissioning / dx.doi.org/10.13182/NT08-A4002