Home / Publications / Journals / Nuclear Technology / Volume 132 / Number 1
Thermal-Hydraulic Design of the Accelerator Production of Tritium Tungsten Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 3-14
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3125
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 15-29
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3126
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 30-48
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3127
Target Systems Overview for the Spallation Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 49-60
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3128
Intensity and Spectra of a White Light Neutron Source Produced by a 70-MeV Proton Accelerator
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 61-65
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3129
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 66-93
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-1
Neutronic Design Studies for the Spallation Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 94-102
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3131
The Accelerator Production of Tritium Materials Test Program
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 103-114
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3132
Target/Blanket Design for the Accelerator Production of Tritium Plant
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 115-127
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3133
Benchmark Calculations for Standard and DUPIC CANDU Fuel Lattices Compared with the MCNP-4B Code
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 128-151
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3134
Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 152-166
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3135
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 167-178
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3136