Number 1 | Number 2 | Number 3
High-Strength High-Efficiency Particulate Air Filters for Nuclear Applications
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 11-29
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety / dx.doi.org/10.13182/NT90-A34483
Application of Circular Filter Inserts
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 30-39
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34484
Filtered Venting for German Power Reactors
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 40-49
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety / dx.doi.org/10.13182/NT90-A34485
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 50-65
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety / dx.doi.org/10.13182/NT90-A34486
Off-Gas Cleaning in an FRG Reprocessing Plant
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 66-76
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Radiation Biology and Environment / dx.doi.org/10.13182/NT90-A34487
Conceptual Design of a Medical Reactor for Neutron Capture Therapy
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 77-92
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor / dx.doi.org/10.13182/NT90-A34488
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 93-105
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor / dx.doi.org/10.13182/NT90-A34489
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 106-117
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor / dx.doi.org/10.13182/NT90-A34490
An Automatic Control Rod Programming Method for a Boiling Water Reactor
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 118-126
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34491
A 3He++ Radio-Frequency Quadrupole Accelerator for Positron Emission Tomography
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 127-133
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT90-A34492
Analysis of a Fluid-Mechanic Model of a Horizontal Tee-Junction
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 134-140
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34493
Analysis of a Nuclear Power Plant Using RELAP5/MOD2 with Modified Bundle Heat Transfer Correlations
Nuclear Technology / Volume 92 / Number 1 / October 1990 / Pages 141-149
Technical Paper / Development of Nuclear Gas Cleaning and Filtering Techniques / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34494
Modification of a Mobile Nuclear Reactor for Medical Diagnosis
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 159-166
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34467
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 167-185
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34468
A Random Sampling Discrete Probability Algorithm with Condensation for Probabilistic Analysis
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 186-193
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34469
RELAP5/MOD2 Analysis of N Reactor Cold-Leg Manifold Break Transient Without Scram
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 194-203
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34470
Fission Product Release from Spent UO2 Fuel Under Uranium-Saturated Oxic Conditions
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 204-213
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34471
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 214-228
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34472
Guidelines for Quality Assurance and Quality Control of Radioactive Wastes
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 229-237
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34473
Modeling on Evaporation Characteristics of a Reprocessing Plant High-Level Liquid Waste Concentrator
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 238-242
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34474
Studies of the Decomposition of Sodium Carbonate in High-Temperature Sodium
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 243-247
Technical Paper / Material / dx.doi.org/10.13182/NT90-A34475
Heat Transfer Modeling in Low Flows and Application to Reflood Heat Transfer
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 248-259
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34476
Study of a Natural-Circulation Boiling Water Reactor with Passive Safety
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 260-268
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34477
Thermal Hydraulics During Boiling in Thermosyphon Evaporators
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 269-281
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34478
Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 282-283
Technical Note / Analyse / dx.doi.org/10.13182/NT90-A34479
Development of Generic In-Service Inspection Priorities for Pressure Boundary Systems
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 291-299
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A16231
Instrumentation and Control Revamping
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 300-308
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A16232
Development and Validation of a Steam Generator Simulation Model
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 309-314
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A16233
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 315-324
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT90-A16234
Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 325-352
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-325
A Model for Fission Gas Release and Fuel Oxidation Behavior for Defected UO2 Fuel Elements
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 353-362
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT90-A16236
Modeling of a Diffusion-Sorption Experiment by Linear and Nonlinear Sorption Isotherms
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 363-373
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A16237
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 374-382
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A16238
Yield Stress Determination by the Massachusetts Institute of Technology Miniaturized Disk Bend Test
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 383-388
Technical Paper / Material / dx.doi.org/10.13182/NT90-A16239
Practical Methods of Measuring Dimensions from Neutron Radiographs of Nuclear Reactor Fuel
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 389-395
Technical Paper / Radiation Application / dx.doi.org/10.13182/NT90-A16240
The Investigation of Conjugate Heat Transfer Phenomena in Advanced Fast Reactors
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 396-410
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A16241
An Integrated Signal Validation System for Nuclear Power Plants
Nuclear Technology / Volume 92 / Number 3 / December 1990 / Pages 411-427
Technical Paper / Instrumentation and Control / dx.doi.org/10.13182/NT90-A16242