Number 1 | Number 2 | Number 3
Reactivity Anomalies in the Fast Flux Test Facility—An Evaluation of Data from Cycles 1 Through 8
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 9-17
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34355
A New Control Strategy for Nuclear Power Reactors
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 18-35
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34356
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 36-51
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34357
A Limit Line for Earthquake Intensity Attenuation
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 52-55
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34358
Experimental and Numerical Investigations of Sodium Boiling Experiments in Pin Bundle Geometry
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 56-82
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34359
A New Safety Approach in the Design of Fast Reactors
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 83-91
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34360
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 92-102
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34361
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 103-115
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34362
Destructive Gamma-Ray Analysis of Fuel Rods from the Taiwan Research Reactor
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 116-125
Technical Paper / Technique / dx.doi.org/10.13182/NT90-A34363
Nuclear Technology / Volume 89 / Number 1 / January 1990 / Pages 126-129
Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT90-A34364
Advances in Technology for Storing Light Water Reactor Spent Fuel
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 141-161
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT90-A34342
Construction of the Monju Prototype Fast Breeder Reactor
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 162-176
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34343
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 177-182
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34344
Development of the SESAME Metallic Fuel Performance Code
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 183-193
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34345
Present Status of Fast Breeder Reactor Fuel Cycle Development at PNC
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 194-202
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34346
A Remote Canister-Positioning and Glass Level Detection System
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 203-216
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34347
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 217-226
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34348
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 227-232
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34349
An Intelligent Stochastic Optimization Routine for Nuclear Fuel Cycle Design
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 233-246
Technical Paper / Technique / dx.doi.org/10.13182/NT90-A34350
Image Reconstruction for a Radiation Field Mapping Device
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 247-251
Technical Paper / Technique / dx.doi.org/10.13182/NT90-A34351
Nuclear Technology / Volume 89 / Number 2 / February 1990 / Pages 252-267
Technical Paper / Education / dx.doi.org/10.13182/NT90-A34352
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 275-280
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34367
An Integrated Operator Advisor System For Plant Monitoring, Procedure Management, and Diagnosis
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 281-317
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34368
Rapid Simulation of Concentration Profiles in Pulsed Column Contactors Using the Purex Process
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 318-327
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT90-A34369
An Incinerator Ash Dissolution Model for the System: Plutonium Oxide, Nitric and Hydrofluoric Acids
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 328-340
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT90-A34370
The Back End of the Nuclear Fuel Cycle: Technical and Economic Analysis—Part I: Once-Through Cycle
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 341-349
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34371
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 350-357
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34372
Dissolution Model for a Glass Having an Adherent Insoluble Surface Layer
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 358-364
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34373
An Alkaline Prefilming Process for the Primary Piping in a New Japanese Boiling Water Reactor
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 365-371
Technical Paper / Material / dx.doi.org/10.13182/NT90-2
Energy Consumption for Product Assay in a Chemical Enrichment Process
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 372-380
Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT90-A34375
Isotopic Backmixing in a Large-Scale Enrichment Column in a Chemical Enrichment Method
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 381-387
Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT90-A34376
Transient Condensation in the Presence of Noncondensables at a Vertical Wall
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 388-398
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34377
Controlled Potential Coulometric Determination of Plutonium in Mixed (U, Pu) Carbide Fuels
Nuclear Technology / Volume 89 / Number 3 / March 1990 / Pages 399-405
Technical Paper / Technique / dx.doi.org/10.13182/NT90-A34378