ANS / Publications / Journals / Nuclear Technology

Verification of a Three-Dimensional Nodal Transient Neutronics Routine for the TRAC-PF1/MOD3 Thermal-Hydraulic System Analysis Code

Bernard R. Bandini, Kostadin N. Ivanov, Anthony J. Baratta, Robert G. Steinke

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 1-20

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2875

Basic Properties of a Zirconia-Based Fuel Material for Light Water Reactors

Claude Degueldre, Jean-Marie Paratte

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 21-29

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2876

Conceptual Design of a Steam-Water Power Reactor Core

Yasunori Bessho, Takashi Nakayama, Michiro Yokomi, Katsuma Nakayama, Hiroki Sano, Nobuhiro Kanazawa

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 30-43

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2877

Biosphere Modeling in Waste Disposal Safety Assessments - An Example Using the Terrestrial-Aquatic Model of the Environment

Richard A. Klos

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 44-59

Technical Paper / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT98-A2878

Vitrification of Cesium-Laden Organic Ion-Exchange Resin in a Stirred Melter

Thomas N. Sargent, Jr., Thomas J. Overcamp, Dennis F. Bickford, Connie A. Cicero-Herman

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 60-66

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2879

Estimating the Alteration Kinetics of the French Vitrified High-Level Waste Package in a Geologic Repository

Patrick Jollivet, Michèle Nicolas, Etienne Vernaz

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 67-81

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2880

Analytical Solutions for Diffusive Mass Transport from a Sphere, Considering a Surface Flux Boundary Condition

B. Peter McGrail

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 82-89

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2881

Numerically Investigating the Influence of Local Flow Behaviors on Flow-Accelerated Corrosion Using Two-Fluid Equations

Kuo-Tong Ma, Yuh-Ming Ferng, Yin-Pang Ma

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 90-102

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT98-A2882

Detection Limits of a Laboratory Pulsed Gamma Neutron Activation Analysis System for the Nondestructive Assay of Mercury, Cadmium, and Lead

Abdul R. Dulloo, Frank H. Ruddy, Thomas V. Congedo, John G. Seidel, Robert J. Gehrke

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 103-112

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT98-A2883

An Approach to Archiving Software-Related Quality Assurance Project Record Files

Lance J. Agee, Robert J. Breen

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 113-115

Technical Note / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2884

Empirical Modeling of U(IV) Distribution in a Nitric Acid-Water-30% TBP/n-Dodecane Biphasic System in the Presence of U(VI), Pu(III), and Hydrazine Nitrate

Shekhar Kumar, Sudhir B. Koganti

Nuclear Technology / Volume 123 / Number 1 / July 1998 / Pages 116-119

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2885

Improved Axial Flux Shape Generator for a Quick Departure from Nucleate Boiling Test

Atul A. Karve, Chae Han, Rizwan-uddin

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 121-129

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT98-A2886

MACSIS: A Metallic Fuel Performance Analysis Code for Simulating In-Reactor Behavior Under Steady-State Conditions

Woan Hwang, Cheol Nam, Thak Sang Byun, Young Cheol Kim

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 130-141

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2887

Investigation of the Premixing Phase of a Steam Explosion with Hot Spheres

Leonhard Meyer, Gustav Schumacher, Helmut Jacobs, Kalman Thurnay

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 142-155

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2888

Effects of Spacer Grids with Mixing Promoters on Reflood Heat Transfer in a PWR LOCA

Zbigniew Koszela

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 156-165

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT98-A2889

Modeling and Control of a Sodium Conversion Process Applied to Nuclear Decommissioning Activities

Humberto E. Garcia

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 166-183

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT98-A2890

Radionuclide Mass Transfer Rates from a Pinhole in a Waste Container for an Inventory-Limited and Constant Concentration Source

Dennis M. LeNeveu

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 184-192

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2891

A Numerical Investigation of Natural Convection Heat Transfer Within Horizontal Spent-Fuel Assemblies

Robert E. Canaan, Dale E. Klein

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 193-208

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2892

Stresses in an Oxidized Zircaloy Cladding Under Quench Conditions: Recalculation of Single-Rod Quench Tests

Helmut Steiner, Monika Heck

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 209-221

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT98-A2893

A New Fuel Management Plan for The Pennsylvania State University TRIGA Reactor Including Supporting Experiments and Calculations

Patrick G. Boyle, Daniel E. Hughes, Samuel H. Levine

Nuclear Technology / Volume 123 / Number 2 / August 1998 / Pages 222-230

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT98-A2894

Pressure- and Flow-Induced Accident and Transient Analyses of a Direct-Cycle, Supercritical-Pressure, Light-Water-Cooled Fast Reactor

Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 233-244

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2895

Conceptual Design of a 50-MW Severe-Accident-Free HTR and the Related Test Program of the HTTR

Kazuhiko Kunitomi, Yukio Tachibana, Akio Saikusa, Kazuhiro Sawa, Lawrence M. Lidsky

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 245-258

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2896

Comparison Between MCNP and Critical Experiments - A Determination of Bias Values to Be Utilized in Licensing Calculations for High-Level Radioactive Waste Disposal

Kenneth D. Wright, James S. Tulenko, Edward T. Dugan

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 259-267

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2897

Use of Weapons-Grade Plutonium in Existing PWRs - Supported by German MOX Recycling Experience

Friedrich Burtak, Gerhard J. Schlosser

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 268-277

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2898

Determination of PWR Control Rod Position by Core Physics and Neural Network Methods

Ninos S. Garis, Imre Pázsit, Urban Sandberg, Tell Andersson

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 278-295

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2899

Temperature Effects on the Leaching Behavior of a High-Level Waste Glass Form

Jiawei Sheng, Shanggeng Luo, Baolong Tang

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 296-303

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2900

Vitrified Waste Form Performance Modeling Applied to the Treatment and Disposal of a Mixed-Waste Sludge at the Savannah River Site

A. Ryan Whited, Robert A. Fjeld, James R. Cook

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 304-319

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2901

Evaluation of Moderator Assemblies for Use in an Accelerator-Based Neutron Source for Boron Neutron Capture Therapy

Jeffrey E. Woollard, Thomas E. Blue, Nilendu Gupta, Reinhard A. Gahbauer

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 320-334

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT98-A2902

Prediction of Liquid Mixture Viscosity for Dry and Water-Saturated TBP/[italic]n[roman]-Dodecane Solutions

Shekhar Kumar, S. B. Koganti

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 335-340

Technical Note / Enrichment / dx.doi.org/10.13182/NT98-A2903

Recovery of Fissile Materials from Wastes and Conversion of the Residual Wastes to Glass

Charles W. Forsberg, Edward C. Beahm

Nuclear Technology / Volume 123 / Number 3 / September 1998 / Pages 341-349

Technical Note / Reprocessing / dx.doi.org/10.13182/NT98-A2904