Home / Publications / Journals / Nuclear Technology / Volume 157 / Number 3
The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 215-229
Technical Paper / Reactivity-Initiated Accident (RIA) / dx.doi.org/10.13182/NT07-A3814
Summary and Interpretation of the CABRI REP-Na Program
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 230-250
Technical Paper / Reactivity-Initiated Accident (RIA) / dx.doi.org/10.13182/NT07-A3815
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 251-260
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3816
Azimuthal Film-Boiling Heat Transfer from a Downward-Facing Hemisphere
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 261-276
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3817
Studies of an Accelerator-Driven Transuranium Burner with Hafnium-Based Inert Matrix Fuel
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 277-298
Technical Paper / Accelerators / dx.doi.org/10.13182/NT07-A3818
Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 299-316
Technical Note / Fission Reactors / dx.doi.org/10.13182/NT07-A3819