Home / Publications / Journals / Nuclear Technology / Volume 149 / Number 1
Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 1-13
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT05-A3575
A New Apparatus for Determination of the Free Volume of a Fuel Rod Using the Double Expansion Method
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 14-21
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT05-A3576
The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 22-48
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT05-A3577
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 49-61
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3578
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 62-70
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3579
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 71-87
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3580
Experimental Research on In-Tube Condensation Under Steady-State and Transient Conditions
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 88-100
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3581
Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 101-109
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT05-A3582
Performance-Based (Risk-Informed) Regulation: A Regulatory Perspective
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 110-121
Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT05-A3583
Review and Research of the Neutron Source Multiplication Method in Nuclear Critical Safety
Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 122-127
Technical Note / Reactor Safety / dx.doi.org/10.13182/NT05-2