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Volume 93

Number 3

A High-Breeding Fast Reactor with Fission Product Gas Purge/Tube-in-Shell Metallic Fuel Assemblies

Toru Hiraoka, Kiyoshi Sako, Hideki Takano, Takeshi Ishii, Mitsuru Sato

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 305-329

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34526

Reactor Design of the Advanced Neutron Source

John M. Ryskamp, Douglas L. Selby, R. Trenton Primm III

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 330-349

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34527

Control Room Habitability During Severe Accidents

Raymond P. Siu

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 350-356

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34528

Studies of Neutron Shielding Properties of Ilmenite-Magnetite Concrete Using A 252Cf Source

S. I. Bhuiyan, F. U. Ahmed, A. S. Mollah, M. A. Rahman

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 357-361

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34529

Numerical Study of Hydrodynamics in Pulsed Solvent Extraction Columns Using the Dynac Code

Masahiro Nabeshima

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 362-374

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A34530

Purex Processing of 10-Year Light Water Reactor Fuel: Flow Sheet

Okan H. Zabunoglu, Bernard I. Spinrad

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 376-381

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A34531

A Method to Evaluate the Maximum Allowable Temperature of Spent Fuel in Dry Storage During a Postulated Accident

Masami Mayuzumi, Takeo Onchi

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 382-388

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34532

Flux and Fluence Determination Using the Material Scrapings Approach

Michael P. Manahan, Sr., Hassan S. Basha

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 389-398

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34533

High-Temperature Corrosion Testing of Alumina and Zirconia in Uranium Hexafluoride Environment

Simon C. P. Wang, Clayton Collins, Samim Anghaie, E. Dow Whitney

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 399-411

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34534

A Step-Heating Dilatometry Method to Measure the Change in Length Due to Annealing of a SiC Temperature Monitor

Toyohiko Yano, Kazunari Sasaki, Tadashi Maruyama, Takayoshi Iseki, Masahiko Ito, Shoji Onose

Nuclear Technology / Volume 93 / Number 3 / March 1991 / Pages 412-415

Technical Note / Material / dx.doi.org/10.13182/NT91-A34535