Home / Publications / Journals / Nuclear Technology / Volume 114 / Number 3
UO2 Core Design of a Direct-Cycle Fast Converter Reactor Cooled by Supercritical Water
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 273-284
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35232
Response Analysis of Electromagnetic Flowmeter
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 285-291
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35233
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 292-307
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35234
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 308-317
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35235
Recent Results on the Solubility of Uranium and Plutonium in Savannah River Site Waste Supernate
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 318-324
Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT96-A35236
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 325-336
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35237
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 337-350
Technical Paper / Material / dx.doi.org/10.13182/NT96-A35238
Pool Boiling from Downward-Facing Curved Surfaces: Effects of Radius of Curvature and Edge Angle
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 351-364
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35239
TRIGA Spent-Fuel Storage Criticality Analysis
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 365-372
Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT96-A35240
Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 373-398
Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT96-A35241
Experimental Investigation of Coupled Natural Circulation Loops
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 399-403
Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35242
Analysis of Routine Radiological Measurements in a Nuclear Power Plant
Nuclear Technology / Volume 114 / Number 3 / June 1996 / Pages 404-412
Technical Note / Radiation Protection / dx.doi.org/10.13182/NT96-A35243