Home / Publications / Journals / Nuclear Technology / Volume 103 / Number 1
Volume 103
Number 1
The Characteristics of the RBMK Core
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 1-9
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34825
Vessel Fluence Assessment with the EFLUVE Code and a Low-Fluence Fuel Management Scheme
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 10-18
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34826
Transient Thermal Analysis of a Space Reactor Power System
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 19-33
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34827
Time Domain Model Sensitivity in Boiling Water Reactor Stability Analysis Using TRAC/BF1
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 34-48
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34828
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 49-65
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34829
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 66-78
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34830
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 79-92
Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34831
Separation and Concentration of Hydrogen Isotopes by a Palladium Alloy Membrane
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 93-100
Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34832
Corrosion Product Particles in Boiling Water Reactor Condensates
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 101-113
Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34833
Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 114-121
Technical Note / Fission Reactor / dx.doi.org/10.13182/NT93-A34834
A Realistic Anticipated Transient Without Scram Evaluation of the Zorita Nuclear Power Plant
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 122-130
Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34835
Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer
Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 131-137
Technical Note / Reactor Operation / dx.doi.org/10.13182/NT93-A34836
