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Volume 23

Number 2

Recent Developments in Nuclear Fuel Cycle Safeguards

William C. Bartels

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

Carleton D. Bingham, Morris W. Lerner

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

R. E. Reed

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

J. M. de Montmollin, T. A. Sellers

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

Thomas E. Sampson, Paul E. Fehlau, Gary M. Worth, Carl N. Henry

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

Darryl D. Jackson, James E. Rein, Glenn R. Waterbury

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

Security Seals for Safeguards

C. Sastre

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

S. Barsali, R. Bovalini, F. Fineschi, B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola

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

C. L. Schuske, D. Dickinson, S. J. Altschuler

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

Grover Tuck

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

T. J. Walker

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