Home / Publications / Journals / Nuclear Technology / Volume 114 / Number 1
Volume 114
Number 1
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
