ANS / Publications / Journals / Nuclear Technology

Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements

Vadim V. Konyashov, Alexander M. Krasnov

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 1-16

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3273

Thorium Fuel Performance in a Tight-Pitch Light Water Reactor Lattice

Taek Kyum Kim, Thomas J. Downar

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 17-29

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3274

Heavy-Metal Aerosol Transport in a Lead-Bismuth-Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation

J. Buongiorno, N. E. Todreas, M. S. Kazimi

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 30-43

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3275

Modeling of Hydrogen Flame Propagation in Multicompartment Buildings

Wison Luangdilok, Hidetsugu Morota, Michael Epstein

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 44-57

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3276

Incorporating Plutonium Particle Size Effects in the Assessment of Active Mode Measurement Uncertainty in Passive-Active Neutron Radioassay Systems

Larry G. Blackwood, Yale D. Harker

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 58-68

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT02-A3277

The Effect of Hydrogen on Oxidative Dissolution of Spent Fuel

Longcheng Liu, Ivars Neretnieks

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 69-78

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT02-A3278

Analysis of External Cooling of the Reactor Vessel During Severe Accidents

Jin Ho Song, Sang Baik Kim, Hee Dong Kim

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 79-89

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3279

An Estimate of the Crust Thickness on the Surface of a Thermally Convecting Liquid-Metal Pool

Askar A. Gubaidullin, Bal Raj Sehgal

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 90-92

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3280

Cost of Electricity from Molten Salt Reactors

R. W. Moir

Nuclear Technology / Volume 138 / Number 1 / April 2002 / Pages 93-95

Technical Note / Economics of Nuclear Systems / dx.doi.org/10.13182/NT02-A3281

Revised Burnup Code System SWAT: Description and Validation Using Postirradiation Examination Data

Kenya Suyama, Hiroki Mochizuki, Takehide Kiyosumi

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 97-110

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3282

Assessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors

Alexander Galperin, Eugene Shwageraus, Michael Todosow

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 111-122

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-21

Advantages of Irradiated DUPIC Fuels from the Perspective of Environmental Impact

Won Il Ko, Ho Dong Kim, Myung Seung Yang

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 123-139

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3284

Lateral Mixing Mechanisms in Vertical and Horizontal Interconnected Subchannel Two-Phase Flows

Sarman Gençay, Alberto Teyssedou, Peter Tye

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 140-161

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT138-140

Chemical Speciation of Iodine Source Term to Containment

Joanna McFarlane, Jungsook C. Wren, Robert J. Lemire

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 162-178

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT138-162

Integrated Analytic Radionuclide Transport Model for a Spent Nuclear Fuel Repository in Saturated Fractured Rock

Allan Hedin

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 179-205

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT02-A3287

Pyrolysis Kinetics of Spent Low-Level Radioactive Resin

Y.-J. Huang, H. Paul Wang, S. H. Liu, M. C. Hsiao

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 206-210

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT02-A3288

A Comparison of Direct Gamma Dose Rates from a Stationary Gaussian Plume Using Different Models

S. Shoaib Raza, Rubén R. Avila

Nuclear Technology / Volume 138 / Number 2 / May 2002 / Pages 211-216

Technical Note / Environmental Science, Technology and Effects / dx.doi.org/10.13182/NT02-A3289

Spatial Control of a Large PHWR via Reduced Model

Dhananjay B. Talange, B. Bandyopadhyay, Akhilanand Pati Tiwari

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 217-237

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT02-A3290

ODS Steel Clad MOX Fuel-Pin Fabrication and Irradiation Performance in EBR-II

James Bottcher, Shigeharu Ukai, Masaki Inoue

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 238-245

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3291

High-Burnup BWR Fuel Behavior Under Simulated Reactivity-Initiated Accident Conditions

Takehiko Nakamura, Kazuyuki Kusagaya, Toyoshi Fuketa, Hiroshi Uetsuka

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 246-259

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3292

A Fission Gas Release Model for High-Burnup LWR ThO₂-UO₂ Fuel

Yun Long, Yi Yuan, Mujid S. Kazimi, Ronald G. Ballinger, Edward E. Pilat

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 260-272

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3293

Thermal-Hydraulic Analyses of Steam Generator Tube Rupture Accident for the Kori Nuclear Unit 1 Pressurized Thermal Shock Study

Soon-Joon Hong, Jae-Hak Kim, Yong-Soo Kim, Goon-Cherl Park

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 273-283

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3294

Transmutation in the Nuclear Fuel Cycle: Approaches and Impacts

Micah D. Lowenthal

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 284-299

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT02-A3295

Neutronics Study on Accelerator Driven Subcritical Systems with Thorium-Based Fuel for Comparison Between Solid and Molten-Salt Fuels

Shunsuke Ishimoto, Kenji Ishibashi, Hideki Tenzou, Toshinobu Sasa

Nuclear Technology / Volume 138 / Number 3 / June 2002 / Pages 300-312

Technical Paper / Accelerators / dx.doi.org/10.13182/NT02-1