Home / Publications / Journals / Nuclear Technology / Volume 157 / Number 1
Volume 157
Number 1
Progress of the DUPIC Fuel Compatibility Analysis - IV: Fuel Performance
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 1-17
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3798
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 18-36
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3799
Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 37-52
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3800
Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 53-64
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3801
Integrator Circuit as an Analogy for Convection
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 65-73
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3802
Water Adsorption Isotherms for Charged and Uncharged Cesium Iodide Aerosol Particles
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 74-86
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT07-A3803
Environmental Impact of Yucca Mountain Repository in the Case of Canister Failure
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 87-105
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3804
Dead-Time Correction for Nonparalyzing Detectors When Measuring Short-Lived Nuclides
Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 106-109
Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT07-A3805
