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Volume 64

Number 2

General Empirical Model for 60Co Generation in Pressurized Water Reactors with Continuous Refueling

Guillermo A. Urrutia, Alberto J. G. Maroto, Roberto Fernández-Prini, Miguel A. Blesa

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 107-114

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33334

Time-Dependent Accident Sequences Including Human Actions

G. Apostolakis, T. L. Chu

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 115-126

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33335

FUMAC—A New Model for Light Water Reactor Fuel Relocation and Pellet-Cladding Interaction

Lewis A. Walton, John E. Matheson

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 127-138

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33336

Fuel/Cladding Chemical Interaction in Mixed-Oxide Fuel at High Burnup

Leo A. Lawrence

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 139-153

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33337

Numerical Analysis of Nuclide Migration Through Fissured Geological Media

Joonhong Ahn, Atsuyuki Suzuki, Ryohei Kiyose

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 154-165

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33338

Guidelines for the Selection of Sites That Might Prove Suitable for Radioactive Waste Disposal on or Beneath the Ocean Floor

R. C. Searle

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 166-174

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33339

Fracture Toughness Behavior of Unirradiated and Irradiated Cr—1 Mo Steel Plate and Weldment

W. J. MILLS

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 175-185

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33340

Turbulent Condensation on a Cold Wall in the Presence of a Noncondensable Gas

Michael L. Corradini

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 186-195

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33341

A Kinetics and Thermal-Hydraulics Capability for the Analysis of Research Reactors

William L. Woodruff

Nuclear Technology / Volume 64 / Number 2 / February 1984 / Pages 196-206

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33342