Home / Publications / Journals / Nuclear Technology / Volume 69 / Number 1
Nuclear Power Plant Site Selection: A Case Study
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 7-13
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33590
Improvements in Compartment Fire Modeling and Simulation of Experiments
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 14-26
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33591
Sensitivity and Uncertainty Analyses for the Accident Sequence Precursor Study
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 27-35
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33592
Radioactive Source Term Models in a Compartment Fire Code
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 36-43
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33593
Status of Qualification of High-Temperature Reactor Fuel Element Spheres
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 44-54
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33594
Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 55-71
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33595
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 72-81
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33596
An Experimental Study of Rod Bundle Dispersed-Flow Film Boiling with High-Pressure Water
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 82-93
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33597
An Empirical Mixing Model for Pressurized Thermal Shock Applications
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 94-99
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33598
Assessment of TRAC Codes with Dartmouth College Countercurrent Flow Tests
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 100-106
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33599
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 107-113
Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33600
Initial Results for the Experimental Evaluation of a Nuclear Waste Repository Source Term Model
Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 114-118
Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33601