Number 1 | Number 2 | Number 3
Validation of MCNP for RBMK Criticality Calculations
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 1-11
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35219
Determination of Core Design Thermal Safety Limits for a Two-Loop Pressurized Water Reactor
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 12-22
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35220
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 23-50
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35221
Analysis of Loss-of-Coolant Accidents in the High-Flux Isotope Reactor
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 51-67
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35222
A Model of Vented Hydrogen Deflagrations in a Containment
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 68-76
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35223
Protection from Radioaerosols and Volatile Radionuclides
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 77-83
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35224
A Comparative Risk Assessment for the Russian V213 Power Reactor
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 84-96
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35225
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 97-110
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35226
Structural Integrity of Spent Nuclear Fuel Storage Casks Subjected to Drop
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 111-121
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35227
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 122-134
Technical Paper / Material / dx.doi.org/10.13182/NT96-A35228
An Analytical Approach to Transient Room Temperature Analysis
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 135-140
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35229
On the Subcooled Critical Flow Model in RELAP5/MOD3
Nuclear Technology / Volume 114 / Number 1 / April 1996 / Pages 141-145
Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35230
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 147-157
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35245
Preliminary Accident Analysis to Support a Passive Depressurization System Design
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 158-168
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35246
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 169-178
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35247
Risk Assessment for Spent-Fuel Pool Cooling at Boiling Water Reactors
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 179-193
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35248
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 194-204
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35249
Computer Modeling of Single-Cell and Multicell Thermionic Fuel Elements
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 205-223
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35250
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 224-234
Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT96-A35251
Near-Field and Far-Field Migration of Radionuclides from a Shallow Land Burial Facility
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 235-245
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35252
Formation of Hot Particles During the Chernobyl Nuclear Power Plant Accident
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 246-253
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35253
Investigation of 14C Release in an Engineered Low-Level Waste Disposal Facility
Nuclear Technology / Volume 114 / Number 2 / May 1996 / Pages 254-271
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35254
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