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The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT84-A33540
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT84-A33521
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT84-A33504
