ANS / Publications / Journals / Nuclear Technology

Beyond-Design-Basis-Accidents Passive Containment-Cooling Spray System

Aly Karameldin, Hassan M. Elsawy Temraz, Nady Attia Ibrahim

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 1-13

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3224

Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code - BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test

Tomoyuki Uwaba, Kosuke Tanaka

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 14-23

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3225

Monitors for the Prediction of Alternate Nuclear Material Concentrations for Pressurized Water Reactor Spent Fuel

William S. Charlton, William D. Stanbro

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 24-36

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3226

Assessment and Application of the ROSE Code for Reactor Outage Thermal-Hydraulic and Safety Analysis

Thomas K. S. Liang, Fu-Kuang Ko, Liang-Che Dai

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 37-49

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3227

Realistic Small- and Intermediate-Break Loss-of-Coolant Accident Analysis Using WCOBRA/TRAC

Stephen M. Bajorek, Nikolay Petkov, Katsuhiro Ohkawa, Robert M. Kemper, Arthur P. Ginsberg

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 50-62

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3228

The Shielding Effect of Iron Louvers for Neutrons and Gamma Rays

Keigo Mio, Tetsuo Kurashige, Toshiso Kosako

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 63-75

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT01-A3229

Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown

Boris K. Bylkin, Galina B. Davydova, Yuri A. Zverkov, Alexander V. Krayushkin, Yuri A. Neretin, Anatoly V. Nosovsky, Valery A. Seyda, Steven M. Short

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 76-88

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT01-A3230

Development of the Process for the Recovery and Conversion of ²³³UF₆ Chemisorbed in NaF Traps from the Molten Salt Reactor Remediation Project

Guillermo D. Del Cul, Alan S. Icenhour, Darrell W. Simmons

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 89-98

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT01-A3231

Unfavorable Conditions for Nuclear Criticality Following Disposal of Transuranic Waste at the Waste Isolation Pilot Plant

Rob P. Rechard, Lawrence C. Sanchez, Holly R. Trellue, Christine T. Stockman

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 99-129

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-3

A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent-Fuel Pool Storage

J. C. Wagner, C. V. Parks

Nuclear Technology / Volume 136 / Number 1 / October 2001 / Pages 130-140

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3233

Studies on the Comprehensive Methodology for Structuring Accident Mitigation Systems for Next-Generation Pressurized Water Reactors

Yonezo Tsujikura

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 141-157

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3234

A Statistical Approach to Predict the Failure Enthalpy and Reliability of Irradiated PWR Fuel Rods During Reactivity-Initiated Accidents

Cheol Nam, Yong-Hwan Jeong, Youn-Ho Jung

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 158-168

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3235

An Integral Response Scaling Method for Reduced-Height Test Facilities and Its Validation Using RELAP5 for Loss of RHR During Midloop Operation

Hyoung Tae Kim, Hee Cheon No

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 169-185

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3236

Thermal-Hydraulic Simulation of Localized Flow Characteristics in a Steam Generator

Yuh-Ming Ferng, Yin-Pang Ma, Jer-Cherng Kang

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 186-196

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3237

A New Method to Determine the Neutron Sensitivity of a Micro Fission Chamber for a Boiling Water Reactor

Atsushi Kimura, Kaoru Fujita, Masaharu Nakazawa, Shinya Fujita, Eiji Seki, Yutaka Tanaka, Shigehiro Kono

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 197-203

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3238

Safety Evaluation of Primary-Side Bleed-and-Feed Scenarios by an Experimental Loss of Feedwater Event at the IIST Facility

Tay-Jian Liu, Show-Chyuan Chiang

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 204-220

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3239

Incipient Fault Detection and Isolation of Field Devices in Nuclear Power Systems Using Principal Component Analysis

Nitin Kaistha, Belle R. Upadhyaya]

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 221-230

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3240

Radiolysis of Bicarbonate and Carbonate Aqueous Solutions: Product Analysis and Simulation of Radiolytic Processes

Zhongli Cai, Xifeng Li, Yosuke Katsumura, Osamu Urabe

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 231-240

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3241

Void Fraction Measurement in Subcooled-Boiling Flow Using High-Frame-Rate Neutron Radiography

Masatoshi Kureta, Hajime Akimoto, Takashi Hibiki, Kaichiro Mishima

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 241-254

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT01-A3242

Coupling Model: A Common-Cause-Failure Model with Consideration of Interpretation Uncertainties

Albert Kreuser, Jörg Peschke

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 255-260

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3243

Preliminary FRAPCON-3Th Steady-State Fuel Analysis of ThO₂ and UO₂ Fuel Mixtures

Eric P. Loewen, Rodrick D. Wilson, Judith K. Hohorst, Arvind S. Kumar

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 261-277

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3244

BWR Reload Strategy Based on Fixing Once-Burnt Fuel Between Cycles

Elizebeth M. Maag, Dave Knott

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 278-291

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3245

Development and Application of the Reactor Coolant On-Line Leakage Evaluation Model for Pressurized Water Reactors

Thomas K. S. Liang, Huan-Jen Hung, Chin-Jang Chang

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 292-300

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3246

Investigating the Stability Characteristics of Natural-Circulation Boiling Water Reactors Using Root Loci of a Reduced-Order Model

Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Hugo van Dam

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 301-314

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3247

Numerical Methodology to Evaluate Fast Reactor Sodium Combustion

Akira Yamaguchi, Takashi Takata, Yasushi Okano

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 315-330

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3248

Kinetic and Statistical Analysis of Primary Circuit Water Chemistry Data in a VVER Power Plant

Gabor Nagy, Péter Tilky, Ákos Horváth, Tamás Pintér, Robert Schiller

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 331-341

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3249

Separation of Actinides from LWR Spent Fuel Using Molten-Salt-Based Electrochemical Processes

Eric J. Karell, Karthick V. Gourishankar, James L. Smith, Lorac S. Chow, Laszlo Redey

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 342-353

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT136-342

Influence of Finite Absorption of Radionuclides on Radionuclide Migration in an Engineered Barrier System

Toshiaki Matsuo, Takuma Yoshida

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 354-366

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3251

The Influence of Lewis Acid/Base Chemistry on the Removal of Gallium by Volatility from Weapons-Grade Plutonium Dissolved in Molten Chlorides

David F. Williams, Guillermo D. Del Cul, Louis M. Toth, Emory D. Collins

Nuclear Technology / Volume 136 / Number 3 / December 2001 / Pages 367-370

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3252