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Volume 67

Number 1

Detection of Control Rod Vibration by Neutron Noise Analysis

Saleem A. Ansari, Syed Khwaja Ayazuddin

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 9-13

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33524

Experimental and Mathematical Simulation Techniques for Determining an In Situ Response Testing Method for Neutron Sensors Used in Reactor Power Plant Protection Systems

Alireza Behbahani, Don W. Miller

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 14-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33525

Noise Source and Reactor Stability Estimation in a Boiling Water Reactor Using a Multivariate Autoregressive Model

Shigeru Kanemoto, Shigeaki Tsunoyama, Yasumasa Andoh, Fumiaki Yamamoto, Shirley A. Sandoz

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 23-37

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33526

Optimization of Boiling Water Reactor Control Rod Patterns Using Linear Search

Takashi Kiguchi, Kazuyori Doi, Takaharu Fukuzaki, Byorn Frogner, Chan Lin, Alexander B. Long

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 38-45

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33527

Combination of Two Spectral Shift Control Methods for Pressurized Water Reactors with Improved Power Utilization

Yigal Ronen, Yaakov Fahima

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 46-55

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33528

Description of the Risø Puff Diffusion Model

Torben Mikkelsen, Søren E. Larsen, Søren Thykier-Nielsen

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 56-65

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33529

A Fuel Rod Debris Packing Model

Jeffrey A. Moore

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 66-72

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33530

The Sodium-Bonding Pin Concept for Advanced Fuels Part II: Analysis of the Cladding Carburization

Claudio Ronchi, Michel Coquerelle, Hubert Blank, Jacques Rouault

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 73-91

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33531

Ion Exchange Adsorption of Radioactive Cesium, Cobalt, Manganese, and Strontium to Granitoid Rocks in the Presence of Competing Cations

Toshiaki Ohe

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 92-101

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33532

Investigations of the Volatilization of Molybdenum and Ruthenium During Subsolidus Sintering of Modified SYNROC-B Crystalline Waste Forms

A. G. Solomah, R. Odoj

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 102-106

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33533

Low-Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods Under Dry Storage Conditions

Robert E. Einziger, Rajiv Kohli

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 107-123

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33534

Interaction of Interstitial Impurities with Radiation-Induced Defects Leading to Improved Elevated Temperature Mechanical Properties of Mild Steel

K. Linga Murty

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 124-131

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33535

A Study of the Reproducibility of Data from Steady-State Tests in Simulated Liquid-Metal Fast Breeder Reactor Fuel Assemblies

A. E. Levin, J. L. Wantland

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 132-148

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33536

A New Universal Formula for Efficiency: Sensitivity to Cooling Conditions of Nuclear and Conventional Power Stations

Nassar H. S. Haidar

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 149-161

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33537

Neutron Resonance Transmission Analysis of Reactor Fuel Samples

James W. Behrens, Ronald G. Johnson, Roald A. Schrack

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 162-168

Technical Paper / Analyse / dx.doi.org/10.13182/NT84-A33538

A Cold-Bottom Supported Vessel for Sodium-Cooled Reactors

Didier Costes

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 169-177

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT84-A33539

Environmental Effects on a Pressure-Activated Switch

T. P. Toepker, J. J. Kelley

Nuclear Technology / Volume 67 / Number 1 / October 1984 / Pages 178-181

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT84-A33540