Home / Publications / Journals / Nuclear Technology / Volume 23 / Number 2
Recent Developments in Nuclear Fuel Cycle Safeguards
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 101-105
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31441
Uranium Assay Requirements of Nuclear Accountability and Safeguards
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 106-111
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31442
Design Concepts Study of a Special Nuclear Material Cargo Vehicle
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 112-116
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31443
A System for Communication with Commercial Special Nuclear Material Shipments
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 117-123
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31444
Portal Monitor for Diversion Safeguards
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 124-131
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31445
Chemical Assay of Plutonium for Safeguards
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 132-141
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31446
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 142-145
Technical Paper / Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard / dx.doi.org/10.13182/NT74-A31447
Removal of Iodine by Sprays in the PSICO 10 Model Containment Vessel
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 146-156
Reactor / Nuclear Safeguards (Presented at November 1973 Meeting) / dx.doi.org/10.13182/NT74-A31448
Surface Density Method Employing Unit Shape Factor (s/v) for the Storage of Fissile Materials
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 157-176
Chemical Processing / Nuclear Safeguards (Presented at November 1973 Meeting) / dx.doi.org/10.13182/NT74-A31449
Simplified Methods of Estimating the Results of Accidental Solution Excursions
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Pages 177-188
Chemical Processing / Nuclear Safeguards (Presented at November 1973 Meeting) / dx.doi.org/10.13182/NT23-177
A Quantitative Strain-and-Stress State Criterion for Failure in the Vicinity of Sharp Cracks
Nuclear Technology / Volume 23 / Number 2 / August 1974 / Page 189
Material / Nuclear Safeguards (Presented at November 1973 Meeting) / dx.doi.org/10.13182/NT74-A31451