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Volume 123

Number 2

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