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Volume 123

Number 1

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

 

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