ANS / Publications / Journals / Nuclear Technology

Monte Carlo Simulation of the LEU-Fueled SLOWPOKE-2 Nuclear Reactor Using MCNP 4A

Martin J. R. Pierre, Hugues W. Bonin

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 1-12

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2928

Modeling the Removal and Retention of Radioiodine by TEDA-Impregnated Charcoal Under Reactor Accident Conditions

Jungsook Clara Wren, Will Long, Chris J. Moore, Keith R. Weaver

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 13-27

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2929

Methyl Iodide Trapping Efficiency of Aged Charcoal Samples from Bruce-A Emergency Filtered Air Discharge Systems

Jungsook Clara Wren, Chris J. Moore, Miyoko Tateishi Rasmussen, Keith R. Weaver

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 28-39

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2930

Generation of Void in a Molten-Metal Bath by Gas Injection from Below

Michael C. Baker, Riccardo Bonazza

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 40-51

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2931

Experiments on Pool Boiling of Water from Downward-Facing Hemispheres

Mohamed S. El-Genk, Cheng Gao

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 52-69

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2932

Optimal Fuzzy Control Design Using Simulated Annealing and Application to Feedwater Heater Control

Kadir Kavaklioglu, Belle R. Upadhyaya

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 70-84

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2933

Vitrification of Borate Waste Generated by Nuclear Power Plants

Jiawei Sheng, Shanggeng Luo, Baolong Tang

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 85-92

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2934

A Novel Waste Form for Disposal of Spent-Nuclear-Fuel Reprocessing Waste: A Vitrifiable Cement

Mary Lou Dunzik Gougar, Barry E. Scheetz, Darryl D. Siemer

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 93-103

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2935

Target and Filter Concepts for Accelerator-Driven Boron Neutron Capture Therapy Applications

James R. Powell, Hans Ludewig, Michael Todosow, Morris Reich

Nuclear Technology / Volume 125 / Number 1 / January 1999 / Pages 104-115

Technical Paper / Accelerators / dx.doi.org/10.13182/NT99-A2936

Detailed Assessment of the Heiss Dampf Reaktor Hydrogen-Mixing Experiments E11

Lothar Wolf, Helmut Holzbauer, Thomas Cron

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 119-135

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2937

Detailed Assessment of the Heiss Dampf Reaktor Hydrogen Deflagration Experiments E12

Lothar Wolf, Ashok Rastogi, Dag Wennerberg, Thomas Cron, Edgar Hansjosten

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 136-154

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2938

Comparisons Between Multidimensional and Lumped-Parameter GOTHIC Containment Analyses with Data

Lothar Wolf, Helmut Holzbauer, Manfred Schall

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 155-165

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2939

GOTHIC Verification on Behalf of the Heiss Dampf Reaktor Hydrogen-Mixing Experiments

Helmut Holzbauer, Lothar Wolf

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 166-181

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2940

Benchmark of the Heiss Dampf Reaktor E11.2 Containment Hydrogen-Mixing Experiment Using the MAAP4 Code

Sung Jin Lee, Chan Y. Paik, Robert E. Henry, Michael Epstein, Martin G. Plys

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 182-196

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2941

CANDU Reactor Simulations Using the Feedback Model with Actinide Burnup History

Mohamed Tahar Sissaoui, Guy Marleau, Daniel Rozon

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 197-212

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2942

Visualization of Simulated Molten-Fuel Behavior in a Pressure Vessel Lower Head Using High-Frame-Rate Neutron Radiography

Hideo Nakamura, Yasuteru Sibamoto, Yoshinari Anoda, Yutaka Kukita, Kaichiro Mishima, Takashi Hibiki

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 213-224

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2943

Wavelet Application in Process Monitoring

Andreas Ikonomopoulos, Akira Endou

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 225-234

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2944

Effects of Perched Water on Thermally Driven Moisture Flow at the Proposed Yucca Mountain Repository for High-Level Waste

Goodluck I. Ofoegbu, Amvrossios C. Bagtzoglou, Ronald T. Green, Michael A. Muller

Nuclear Technology / Volume 125 / Number 2 / February 1999 / Pages 235-253

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2945

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - I: Methodology Overview

Dale B. Lancaster, Emilio Fuentes, Chi H. Kang, Meraj Rahimi

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 255-270

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2946

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - II: Validation

Emilio Fuentes, Dale B. Lancaster, Meraj Rahimi

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 271-291

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2947

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - III: Bounding Treatment of Spatial Burnup Distributions

Chi H. Kang, Dale B. Lancaster

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 292-304

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2948

Experimental and Computational Study of the Core Inlet Temperature Pattern Under Asymmetric Loop Conditions

Kil-Sup Um, Seok-Hee Ryu, Yong-Seog Choi, Goon-Cherl Park

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 305-315

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2949

Effects of Magnesium and Zinc Additives on Corrosion and Cobalt Contamination of Stainless Steels in Simulated BWR Coolant

D. H. Lister, G. Venkateswaran

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 316-331

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2950

Influence of Increased Temperature from Cement Hydration on Aluminum Corrosion Prevention When LiNO₃ is Added to the Cement

Toshiaki Matsuo, Takashi Nishi, Tatsuo Izumida, Masami Matsuda

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 332-336

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2951

The Interaction of Iodine with Organic Material in Containment

Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 337-362

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT99-A2952

Large-Scale Experiments on Ex-Vessel Core Melt Behavior

Manfred Sappok, Wolfgang Steinwarz

Nuclear Technology / Volume 125 / Number 3 / March 1999 / Pages 363-370

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT99-A2953