ANS / Publications / Journals / Nuclear Technology

Stability Monitoring Tests Using a Nuclear-Coupled Boiling Channel Model

Miguel Ceceñas-Falcón, Robert M. Edwards

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 1-11

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3100

Theoretical Derivation of Simplified Evaluation Models for the First Peak of a Criticality Accident in Nuclear Fuel Solution

Yasushi Nomura

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 12-21

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3101

Fission-Product Release During Transient Heating of Irradiated CANDU Fuel

Zhendong Liu, Raymond S. Dickson, Lawrence W. Dickson, Zoran Bilanovic, David S. Cox

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 22-35

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3102

Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

Kazuo Minato, Kazuhiro Sawa, Toshio Koya, Takeshi Tomita, Akiyoshi Ishikawa, Charles A. Baldwin, William Alexander Gabbard, Charlie M. Malone

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 36-47

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3103

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II

Atul A. Karve, Paul J. Turinsky

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 48-68

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3104

Application of the Two-Dimensional Navier-Stokes Equations to Steam Cooling in Asymmetrically Heated Channels

L. W. Ward

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 69-81

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3105

Analysis of PANDA Passive Containment Cooling Steady-State Tests with the Spectra Code

Marek M. Stempniewicz

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 82-101

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3106

Current State of Knowledge of Water Radiolysis Effects on Spent Nuclear Fuel Corrosion

H. Christensen, S. Sunder

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 102-123

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3107

Thermal Modeling and Performance Analysis of Interim Dry Storage and Geologic Disposal Facilities for Spent Nuclear Fuel

Si Y. Lee, Robert L. Sindelar, David C. Losey

Nuclear Technology / Volume 131 / Number 1 / July 2000 / Pages 124-151

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3108

The Impact of the Steam-Water Mixture Heterogeneity on the Results of Boiling Water Reactor Cell Calculations

Alexander O. Goltsev, Dmitry N. Martynov, Stanislav V. Marin, Andrei A. Lekomtsev

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 153-158

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3109

Development of a Code with the Capability of Internal Assessment of Uncertainty

Francesco D'Auria, Walter Giannotti

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 159-196

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-5

Parametric Studies on Plutonium Transmutation Using Uranium-Free Fuels in Light Water Reactors

Afroza Shelley, Hiroshi Akie, Hideki Takano, Hiroshi Sekimoto

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 197-209

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3111

Calculated Actinide and Fission Product Concentration Ratios for Gaseous Effluent Monitoring Using Monteburns 3.01

William S. Charlton, Robert T. Perry, Bryan L. Fearey, Theodore A. Parish

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 210-227

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3112

VVER1000/320 Operational Transient Simulation with the CATHARE Computer Program

Andrey A. Troshko, Yassin A. Hassan

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 228-238

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3113

Localization of a Vibrating Control Rod Pin in Pressurized Water Reactors Using the Neutron Flux and Current Noise

Vasiliy Arzhanov, Imre Pázsit, Ninos S. Garis

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 239-251

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT00-A3114

Rethinking High-Level Waste Disposal: Separate Disposal of High-Heat Radionuclides (⁹⁰Sr and ¹³⁷Cs)

Charles W. Forsberg

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 252-268

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3115

Prediction of In-Phantom Dose Distribution Using In-Air Neutron Beam Characteristics for Boron Neutron Capture Synovectomy

Jérôme M. Verbeke, Allen S. Chen, Jasmina L. Vujic, Ka-Ngo Leung

Nuclear Technology / Volume 131 / Number 2 / August 2000 / Pages 269-276

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT00-A3116

Temperature Reactivity Effects in Pebbles of a High-Temperature Reactor Fueled with Reactor-Grade Plutonium

E. E. Bende

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 279-296

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3117

LOCA with Consequential or Delayed LOOP: Modeling of Accident Sequences and Associated Core Damage Frequency

Gerardo Martinez-Guridi, Pranab Samanta, Tsong-Lun Chu, Ji-Wu Yang

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 297-318

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3118

Analysis of Kuosheng Large-Break Loss-of-Coolant Accident with MELCOR 1.8.4

Te-Chuan Wang, Shih-Jen Wang, Chun-Sheng Chien

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 319-331

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3119

Formulas Giving Buildup Factor for Double-Layered Shields

Mevlut Guvendik, Nicholas Tsoulfanidis

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 332-336

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT00-A3120

Effect of Depleted-Uranium Dioxide Particulate Fill on Spent-Nuclear-Fuel Waste Packages

Charles W. Forsberg

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 337-353

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3121

The Remodeling and Basic Characteristics of the Heavy Water Neutron Irradiation Facility of the Kyoto Univesity Research Reactor, Mainly for Neutron Capture Therapy

Tooru Kobayashi, Yoshinori Sakurai, Keiji Kanda, Yoshiaki Fujita, Koji Ono

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 354-378

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT00-A3122

University Research Reactors: Issues and Challenges

John A. Bernard, Lin-Wen Hu

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 379-384

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT00-A3123

The Physics of Plutonium Fuels - A Review of Organization for Economic Cooperation and Development/Nuclear Energy Agency Activities

Kevin Hesketh, Marc Delpech, Enrico Sartori

Nuclear Technology / Volume 131 / Number 3 / September 2000 / Pages 385-394

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3124