American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 49 / Number 2

Volume 49

Number 2

Liquid-Metal Fast Breeder Reactor Vented Assembly Hydraulic Modeling and Testing

James C. F. Wang, Allen E. Dubberley

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 186-195

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32481

A Continuous Glass Melter for Immobilization of Radioactive Waste

C. C. Chapman, J. L. Buelt

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 196-208

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32482

The Fixation of Radioiodine with Portland Cement. Part II: Radiation Stability Tests

Walter E. Clark, William B. Howerton

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 209-213

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32483

Dynamic Process Model of a Plutonium Oxalate Precipitator

G. M. Borgonovi, J. E. Hammelman, C. L. Miller

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 214-222

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32484

Alpha Waste Production and Proliferation Hazard of Different Fuel Cycles

Robert P. Schuman

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 223-232

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32485

A Production Facility for the Solidification of High-Level Radioactive Wastes

G. E. Bingham, B. R. Wheeler

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 233-242

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32486

Separation of Americium, Curium, and Trivalent Lanthanides from High-Level Wastes by Oxalate Precipitation: Experiments with Synthetic Waste Solutions

Charles W. Forsberg

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 243-252

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32487

The Sorption of Technetium and Iodine Radioisotopes by Various Minerals

R. Strickert, A. M. Friedman, S. Fried

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 253-266

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32488

Full-Scale In-Can Melting for Vitrification of Nuclear Wastes

H. Thomas Blair

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 267-273

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32489

Spent Fuel Heatup Following Loss of Water During Storage

Allen S. Benjamin, David J. McCloskey

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 274-294

Nuclear Fuel Cycle / Fuel Cycle / dx.doi.org/10.13182/NT80-A32490

Protection of Nuclear Power Plants Against Seism

C. Plichon, R. Gueraud, M. H. Richli, J. F. Casagrande

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 295-306

Nuclear Fuel Cycle / Reactor / dx.doi.org/10.13182/NT80-A32491

The Use of Yttrium for the Recovery of Tritium from Lithium at Low Concentrations

Robert E. Buxbaum, Ernest F. Johnson

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 307-314

Nuclear Fuel Cycle / Chemical Processing / dx.doi.org/10.13182/NT80-A32492

BeH2 as a Moderator in Minimum Critical Mass Systems

K. Subba Rao, M. Srinivasan

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 315-320

Technical Note / Reactor / dx.doi.org/10.13182/NT80-A32493

Application of Sol-Gel Technology to Fixation of Nuclear Reactor Waste

W. J. Lackey, R. E. Blanco, A. L. Lotts

Nuclear Technology / Volume 49 / Number 2 / July 1980 / Pages 321-324

Technical Note / Radioactive Waste / dx.doi.org/10.13182/NT80-A32494