American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 67

Volume 67

Number 1 | Number 2 | Number 3

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

Number 2

  • Table of Contents
  • Authors(Daniel Cubicciotti, Bal Raj Sehgal, R. E. Williford, Naohito Uetake, Yoshihiro Ozawa, Makoto Kikuchi, Joe L. Ratigan, A. Saltelli, A. Avogadro, G. Bidoglio, Roger Thunvik, Carol Braester, S. V. Panno, P. Soo, Willem L. Zijp, Éva M. Zsolnay, Henk J. Nolthenius, Egon J. Szondi, Gerardus C. H. M. Verhaag, Vincent P. Manno, Michael W. Golay, August W. Cronenberg, Douglas W. Croucher, Phililp E. MacDonald, Roald A. Schrack, Randall R. Nason)

Vaporization of Core Materials in Postulated Severe Light Water Reactor Accidents

Daniel Cubicciotti, Bal Raj Sehgal

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 191-207

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33510

A Cracked-Fuel Constitutive Equation

R. E. Williford

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 208-220

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33511

High-Level Radioactive Waste Glass Synthesis at Low Temperatures

Naohito Uetake, Yoshihiro Ozawa, Makoto Kikuchi

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 221-227

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33512

A Sensitivity Study of Brine Transport into a Borehole Containing a Commercial High-Level Waste Canister

Joe L. Ratigan

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 228-244

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33513

Americium Filtration in Glauconitic Sand Columns

A. Saltelli, A. Avogadro, G. Bidoglio

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 245-254

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33514

Radioactive Waste Repositories in Hard Rock Aquifers—Hydrodynamic Aspects

Roger Thunvik, Carol Braester

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 255-267

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33515

Potential Effects of Gamma Irradiation on the Chemistry and Alkalinity of Brine in High-Level Nuclear Waste Repositories in Rock Salt

S. V. Panno*, P. Soo

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 268-281

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33516

Intercomparison of Predicted Displacement Rates Based on Neutron Spectrum Adjustments (REAL-80 Exercise)

Willem L. Zijp, Éva M. Zsolnay, Henk J. Nolthenius, Egon J. Szondi, Gerardus C. H. M. Verhaag

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 282-301

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33517

Application of the LIMIT Code to the Analysis of Containment Hydrogen Transport

Vincent P. Manno, Michael W. Golay

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 302-311

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33518

Fuel Foaming and Collapse During Light Water Reactor Core Meltdown Accidents

August W. Cronenberg, Douglas W. Croucher, Philip E. MacDonald

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 312-325

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33519

Uranium-235 Measurement in Waste Material by Resonance Neutron Radiography

Roald A. Schrack

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 326-332

Technical Paper / Analyse / dx.doi.org/10.13182/NT84-A33520

Numerical Simulation of Photon Response in Portal Monitors

Randall R. Nason*

Nuclear Technology / Volume 67 / Number 2 / November 1984 / Pages 333-340

Technical Paper / Technique / dx.doi.org/10.13182/NT84-A33521

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