Number 1
Detection of Control Rod Vibration by Neutron Noise Analysis
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 9-13
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33524
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 14-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33525
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
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 38-45
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33527
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
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
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
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 73-91
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33531
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 92-101
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33532
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 102-106
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33533
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 107-123
Technical Paper | Material | doi.org/10.13182/NT84-A33534
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 124-131
Technical Paper | Material | doi.org/10.13182/NT84-A33535
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 132-148
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33536
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
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
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
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 178-181
Technical Note | Fission Reactor | doi.org/10.13182/NT84-A33540
Number 2
Vaporization of Core Materials in Postulated Severe Light Water Reactor Accidents
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
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
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 221-227
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33512
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
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
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 255-267
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33515
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 268-281
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33516
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
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
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
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
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 333-340
Technical Paper | Technique | doi.org/10.13182/NT84-A33521
Number 3
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 348-359
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33494
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
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 381-406
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33496
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 407-410
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33497
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
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
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 429-436
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33500
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
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 452-462
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33502
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 463-472
Technical Paper | Analyse | doi.org/10.13182/NT84-A33503
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 473-477
Technical Paper | Technique | doi.org/10.13182/NT84-A33504