ANS / Publications / Journals / Nuclear Technology

ATBR - A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium Reactor

V. Jagannathan, Usha Pal, R. Karthikeyan, S. Ganesan, R. P. Jain, S. U. Kamat

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 1-32

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT01-A3156

Kinetics of Gaseous Iodine Uptake onto Stainless Steel During Iodine-Assisted Corrosion

Jungsook Clara Wren, Glenn A. Glowa

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 33-49

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3157

Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident Conditions

Toyoshi Fuketa, Hideo Sasajima, Tomoyuki Sugiyama

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 50-62

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3158

Experimental Investigation of Mixing Phenomena Inside a Concrete Containment Cooled by an Innovative Passive System

Luigi Brusa, Alessandro Bianchi, Giancarlo Fruttuoso, Antonio Manfredini, Francesco Oriolo, Mario D. Carelli, Robert P. Kendig, Fred E. Peters

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 63-76

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3159

Investigation of Core Thermohydraulics in Fast Reactors - Interwrapper Flow During Natural Circulation

H. Kamide, K. Hayashi, T. Isozaki, M. Nishimura

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 77-91

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3160

Evaluation of Impurity Behavior in the Reactor Water of a Boiling Water Reactor

Hiroo Igarashi, Nobuyuki Ohta, Naoshi Usui, Katsumi Ohsumi, Shunsuke Uchida, Tsuneo Matsui

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 92-102

Technical Paper / Nuclear Plant Operation and Control / dx.doi.org/10.13182/NT01-A3161

Removal of Zirconium in Electrometallurgical Treatment of Experimental Breeder Reactor II Spent Fuel

Rajesh K. Ahluwalia, Thanh Q. Hua, Howard K. Geyer

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 103-118

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT01-A3162

Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated Water

Yasuteru Sibamoto, Hideo Nakamura, Yoshinari Anoda

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 119-132

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT01-A3163

Assessment of TRAC-BF1 for Waterhammer Calculations with Entrapped Air

Kevin W. Brinckman, Mark A. Chaiko

Nuclear Technology / Volume 133 / Number 1 / January 2001 / Pages 133-139

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3164

Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGR

Shigeaki Nakagawa, Akio Saikusa, Kazuhiko Kunitomi

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 141-152

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT01-A3165

PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods

Sergei Lemehov, Jinichi Nakamura, Motoe Suzuki

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 153-168

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3166

Multidimensional TMI-1 Main-Steam-Line-Break Analysis Methodology Using TRAC-PF/NEM

Kostadin N. Ivanov, Tara M. Beam, Anthony J. Baratta, Ardesar Irani, Nicholas G. Trikouros

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 169-186

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3167

Assessment of the ATHENA Code for Calculating the Void Fraction of a Lead-Bismuth/Steam Mixture in Vertical Upflow

Cliff B. Davis

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 187-193

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3168

Corium Oxidation at Temperatures Above 2000 K

Donald L. Hagrman, Joy L. Rempe

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 194-212

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3169

Neural Network with Local Memory for Nuclear Reactor Power Level Control

Önder Uluyol, Magdi Ragheb, Lefteri Tsoukalas

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 213-228

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3170

Transmutation of Elemental Cesium by a Fusion Neutron Source

Masaki Saito, Vladimir A. Apse, Vladimir V. Artisyuk, Anatolii N. Chmelev

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 229-241

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3171

Concepts in Waste Management: Cerium-Promoted Dissolution of Refractory Actinide Oxides

Daniel William Tedder, Bruce C. Finney

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 242-252

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3172

Modeling of Hydrodynamic Chromatography for Colloid Migration in Fractured Rock

Shih-Hai Li, Chun-Ping Jen

Nuclear Technology / Volume 133 / Number 2 / February 2001 / Pages 253-263

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3173

Application of the Integrated TH-PA Method to the Westinghouse AP600 Design

Yue Guan, Fei Li, Mohammad Modarres, David Bessette, Marino Dimarzo

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 269-289

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3174

A Method of Integrating Thermal-Hydraulic Analysis and Probabilistic Assessment for Safety Evaluation and Screening

Yue Guan, Fei Li, Mohammad Modarres

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 290-309

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3175

Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water Reactors

Felix C. Difilippo, Stephen E. Fisher

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 310-324

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3176

A Modification of the Inner and Outer Core for Reactor Pressure Vessel Lifetime Extension

Bo Kyun Seo, Jong Kyung Kim, Chang Ho Shin, Tae Je Kwon

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 325-337

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3177

Prediction of a Breakthrough Curve of Iodine on a Reduced Silver-Loaded Adsorbent Bed

Kenji Takeshita, Yoshio Nakano

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 338-345

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT01-A3178

Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear Data

Mafizur Rahman, Hideki Takano

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 346-354

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT01-A3179

Development Program of LOCA Licensing Calculation Capability with RELAP5-3D in Accordance with Appendix K of 10 CFR 50.46

Thomas K. S. Liang, Richard R. Schultz

Nuclear Technology / Volume 133 / Number 3 / March 2001 / Pages 355-358

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3180