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Volume 117
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
