Home / Publications / Journals / Nuclear Technology / Volume 111 / Number 2
Estimation and Interpretation of keff Confidence Intervals in MCNP
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 169-182
Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35128
Validation of KENO V.a with ENDF/B-V Cross Sections for 233U Systems
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 183-196
Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35129
Analyses of Hypothetical Nuclear Criticality Excursions in 10- and 20-MW Freezer/Sublimer Vessels
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 197-218
Technical Paper / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35130
Analysis of a Hypothetical Criticality Accident in a Waste Supercompactor
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 219-226
Technical Paper / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35131
Improved Dose Estimates for Nuclear Criticality Accidents
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 227-240
Technical Note / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35132
Thermal Hydraulics of an External Water Wall Type Passive Containment Cooling System
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 241-250
Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35133
Dynamic Stability of a Fluidized-Bed Nuclear Reactor
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 251-259
Technical Paper / Nuclear Criticality Safety Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35134
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 260-269
Technical Paper / Nuclear Criticality Safety Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35135
Three-Dimensional Neutron Flux Calculations for the VVER Pressure Vessel
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 270-274
Technical Paper / Nuclear Criticality Safety Special / Material / dx.doi.org/10.13182/NT95-A35136
Flashing and Heat Transfer During Outsurge Transients in a Small Pressurizer
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 275-282
Technical Paper / Nuclear Criticality Safety Special / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35137
Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 283-302
Technical Paper / Nuclear Criticality Safety Special / Reactor Operation / dx.doi.org/10.13182/NT95-A35138