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Volume 67

Number 3

The Logic Flowgraph: A New Approach to Process Failure Modeling and Diagnosis for Disturbance Analysis Applications

Sergio Guarro, David Okrent

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 348-359

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33494

Reactivity and Reaction Rate Ratio Changes with Moderator Voidage in a Light Water High Converter Reactor Lattice

Rakesh Chawla, Kurt Gmür, Helmut Hager, Rudolf Seiler

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 360-380

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33495

Consequence Analysis of a Steam Generator Tube Rupture Accident

James M. Wu, Chun-Fa Chuang

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 381-406

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33496

Thermodynamical Calculations on the Behavior of Gaseous Iodine Species Following a Hypothetical Severe Light Water Reactor Accident

Rolf Hahn, Hans J. Ache

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 407-410

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33497

Pontryagin’s Optimal Control Principle Applied to Computer-Assisted Accident Diagnostics in Nuclear Power Plants

Gerald R. Mazetis, David D. Ebert

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 411-418

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33498

The Leaching Behavior of a Glass Waste Form — Part I: The Characteristics of Surface Layers

Takashi Murakami, Tsunetaka Banba

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 419-428

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33499

A Pelletizing Model and Its Application to Radioactive Waste Treatment

Koichi Chino, Masami Matsuda, Fumio Kawamura, Hideo Yusa, Susumu Horiuchi, Makoto Kikuchi

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 429-436

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33500

The Development of a Gamma-Ray Scattering Densitometer for the Nonintrusive Measurement of Local Void Fraction

Katsuhiro Ohkawa, Richard T. Lahey, Jr.

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 437-451

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33501

Convection-Radiation Heat Transfer to Steam in Rod Bundle Geometry

Ahmet Sozer, Thomas M. Anklam, H. L. Dodds, Jr.

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 452-462

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33502

A Comparison of Theoretical and Experimental Calibration of a Highly Collimated Mobile Gamma-Ray Spectrometer

Gary L. Catchen, Amos Notea, Brian C. Campbell

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 463-472

Technical Paper / Analyse / dx.doi.org/10.13182/NT84-A33503

Some Considerations in the Use of an A Priori Mathematical Model to Fit a Nuclear Utility’s Thermoluminescence Dosimetry Data

William H. Harding, Carl A. Silver

Nuclear Technology / Volume 67 / Number 3 / December 1984 / Pages 473-477

Technical Paper / Technique / dx.doi.org/10.13182/NT84-A33504