Home / Publications / Journals / Nuclear Technology / Volume 63 / Number 2
Experimental Studies on the Use of Liquid Lead in a Molten Salt Nuclear Reactor
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 197-208
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33280
The Nuclear Reactor Strategy Between Fast Breeder Reactors and Advanced Pressurized Water Reactors
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 209-214
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33281
An Axially Heterogeneous Core Concept for Large LMFBRs and Its HCDA Behavior
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 215-227
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33282
Commercial Nuclear Fuel Reprocessing Applying the SAFAR Processing Concept
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 228-243
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33283
Operability and Maintainability of the Barnwell Nuclear Fuel Plant: A Key Issue
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 244-253
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33284
Postirradiation Behavior of UO2 Fuel I: Elements at 220 to 250°C in Air
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 254-265
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33285
The Reduction of Neptunium(VI) by Basalt and Olivine
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 266-270
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33286
Electrodecontamination of Glove-Box Materials
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 271-285
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33287
The Nuclear Reactor Strategy Between Light Water Reactors and Advanced Pressurized Water Reactors
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 286-294
Technical Paper / Economic / dx.doi.org/10.13182/NT83-A33288
A New Postirradiation Mechanical Behavior Test—The Miniaturized Disk Bend Test
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 295-315
Technical Paper / Material / dx.doi.org/10.13182/NT83-A33289
Heat Removal Tests for Pressurized Water Reactor Containment Spray by Large-Scale Facility
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 316-329
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33290
SIMMER-II Recriticality Analyses for a Homogeneous Core of the 300-MW(electric) Class
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 330-336
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33291
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 337-346
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33292
Nuclear Criticality Safety Considerations in Design of Dry Fuel Assembly Storage Arrays
Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 347-350
Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT83-A33293