Volume 117
Number 1 | Number 2 | Number 3
Number 1
Test Results of Ya-21u Thermionic Space Power System
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 1-14
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35332
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 15-39
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35333
How the Code Analyst Can Influence the Calculation and Use Good Practices to Minimize Pitfalls
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 40-48
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35334
An Assessment of Ex-Vessel Fuel/Coolant Interaction Energetics for Advanced Light Water Reactors
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 49-63
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35335
The Safety Concerns of Spent-Fuel Pool Reracking in Taiwan’s Maanshan Nuclear Power Station
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 64-79
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35336
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 80-86
Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT97-A35337
A Computational Model for Thermal Fluid Design Analysis of Nuclear Thermal Rockets
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 87-108
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35338
Posttest Calculations of Bundle Quench Test CORA-13 with ATHLET-CD
Nuclear Technology / Volume 117 / Number 1 / January 1997 / Pages 109-123
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35339
Number 2
A Pressurized Water Reactor Design for Plutonium Incineration: Fuel Cycle Options
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 125-132
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35319
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 133-150
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35320
Mechanical Efficiency of the Energy Release During a Steam Explosion
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 151-157
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35321
Material Distribution in Light Water Reactor-Type Bundles Tested Under Severe Accident Conditions
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 158-170
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35322
Transuranium Fuel Assembly for Transmutation in a Pressurized Water Reactor
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 171-183
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35323
Boiling Water Reactor Benchmark Calculations
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 184-194
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35324
Melting Tests for Recycling Slightly Radioactive Metallic Wastes Arising from Decommissioning
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 195-205
Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT97-A35325
Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 206-222
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35326
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 223-233
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35327
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 234-247
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35328
Criticality Safety Assessment of a TRIGA Reactor Spent-Fuel Pool Under Accident Conditions
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 248-254
Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT97-A35329
Virtual Radiation Fields—A Virtual Environment Tool for Radiological Analysis and Simulation
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 255-266
Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT97-A35330
Number 3
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 267-280
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35341
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 281-292
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35342
Transmutation of Technetium and Iodine—Irradiation Tests in the Frame of the EFTTRA Cooperation
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 293-298
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35343
Studies on the Restructuring of Fast Breeder Test Reactor Fuel by Out-of-Pile Simulation
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 299-305
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35344
Local Analysis Technique for the Advanced Neutron Source Reactor Fuel Defect Studies
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 306-315
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35345
Transport of Weapons-Grade Plutonium and Boron Through Fractured Geologic Media
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 316-328
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35346
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 329-339
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35347
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 340-352
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35348
Moisture Fraction Measurements for Two-Phase Mist Flow Using High-Sensitivity Capacitance Sensors
Nuclear Technology / Volume 117 / Number 3 / March 1997 / Pages 353-365
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35349
