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Volume 49

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Number 1

Table of Contents
Authors(G. L. Cano, R. W. Ostensen, M. F. Young, A. M. Sokolovsky, M. Livolant, J. Gauvain, A. Hoffmann, M. Baines, S. J. Board, N. E. Buttery, R. W. Hall, S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes, Marilyn M. Osterhout, R. T. Lahey, Jr., P. S. Kamath, S. R. Speidel, W. H. Plettenberg, H. J. Sutherland, J. E. Smaardyk, L. A. Kent, Dong H. Nguyen, G. W. Hollenberg, J. L. Jackson, J. A. Basmajian, David W. Varela, William E. Kastenberg, Vijay K. Dhir, P. Wydler, W. Heer, P. Stiller, H. U. Wenger, M. V. Ramaniah, H. C. Jain, S. K. Aggarwal, S. A. Chitambar, V. D. Kavimandan, A. I. Almaula, P. M. Shah, A. R. Parab, V. L. Sant, A. Delbrassine, L. Smith, J. M. Beeston, R. R. Hobbins, G. W. Gibson, W. C. Francis, H. C. Burkholder, E. L. J. Rosinger, T. V. Krishnan, R. J. Gehrke, J. I. Anderson, D. H. Meikrantz)
Textbook of Nuclear Medicine: Basic Science(Dennis Patton)
Professional Engineer’s License Guide(David J. Hall, P.E.)
World Energy—Looking Ahead to 2020(Robert A. Fjeld)

Visual In-Pile Fuel Disruption Experiments

G. L. Cano, R. W. Ostensen, M. F. Young

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 9-18

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32501

Study of Progressive Damage to Reinforced Concrete Structures Submitted to Dynamic Reversed Load

A. M. Sokolovsky, M. Livolant, J. Gauvain, A. Hoffmann

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 19-26

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32502

The Hydrodynamics of Large-Scale Fuel-Coolant Interactions

M. Baines, S. J. Board, N. E. Buttery, R. W. Hall

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 27-39

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32503

Critical Experiments with Concrete-Reflected Fast Test Reactor Fuel Pins in Water

S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 40-46

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32504

Control of Oxygen, Hydrogen, and Tritium in Sodium Systems at Experimental Breeder Reactor II

Marilyn M. Osterhout

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 47-50

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32505

The Analysis of Boiling Water Reactor Long-Term Cooling

R. T. Lahey, Jr., P. S. Kamath

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 51-60

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32506

Development of a Removable Closure for Large Cavities in High Temperature Reactor Prestressed Concrete Reactor Vessels

S. R. Speidel, W. H. Plettenberg

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 61-69

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32507

Acoustic Measurement of Penetration of Liquid Sodium into Limestone Concrete

H. J. Sutherland, J. E. Smaardyk, L. A. Kent

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 70-79

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32508

The Uncertainty in Accident Consequences Calculated by Large Codes due to Uncertainties in Input

Dong H. Nguyen

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 80-91

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32509

In-Reactor Measurement of Neutron Absorber Performance

G. W. Hollenberg, J. L. Jackson, J. A. Basmajian

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 92-101

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32510

Implications of In-Channel Plugging During Fast Reactor Overpower Excursions

David W. Varela, William E. Kastenberg, Vijay K. Dhir

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 102-114

Technical Paper / Nuclear Power Reactor Safety / Reactor Siting / dx.doi.org/10.13182/NT80-A32511

A Uranium-Plutonium-Neptunium Fuel Cycle to Produce Isotopically Denatured Plutonium

P. Wydler, W. Heer, P. Stiller, H. U. Wenger

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 115-120

Technical Paper / Nuclear Power Reactor Safety / Fuel Cycle / dx.doi.org/10.13182/NT80-A32512

Isotope Dilution Alpha Spectrometry for the Determination of Plutonium Concentration in Irradiated Fuel Dissolver Solution: IDAS and R-IDAS

M. V. Ramaniah, H. C. Jain, S. K. Aggarwal, S. A. Chitambar, V. D. Kavimandan, A. I. Almaula, P. M. Shah, A. R. Parab, V. L. Sant

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 121-128

Technical Paper / Nuclear Power Reactor Safety / Chemical Processing / dx.doi.org/10.13182/NT80-A32513

Pellet and Sphere-Pac (U,Pu)C Fuel Comparative Irradiation Tests

A. Delbrassine, L. Smith

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 129-135

Technical Paper / Nuclear Power Reactor Safety / Fuel / dx.doi.org/10.13182/NT80-A32514

Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors

J. M. Beeston, R. R. Hobbins, G. W. Gibson, W. C. Francis*

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 136-149

Technical Paper / Nuclear Power Reactor Safety / Fuel / dx.doi.org/10.13182/NT80-A32515

A Model for the Transport of Radionuclides and Their Decay Products Through Geologic Media

H. C. Burkholder, E. L. J. Rosinger

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 150-158

Technical Paper / Nuclear Power Reactor Safety / Radioactive Waste / dx.doi.org/10.13182/NT80-A32516

Intensity Measurements in X-Ray Fluorescence Analysis

T. V. Krishnan

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 159-164

Technical Paper / Nuclear Power Reactor Safety / Instrument / dx.doi.org/10.13182/NT80-A32517

Measurement of the Ge(Li) Detector Efficiency for Gas Bomb Geometries

R. J. Gehrke, J. I. Anderson*, D. H. Meikrantz

Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 165-173

Technical Paper / Nuclear Power Reactor Safety / Analysis / dx.doi.org/10.13182/NT80-A32518

Number 2

Table of Contents
Authors(James C. F. Wang, Allen E. Dubberley, C. C. Chapman, J. L. Buelt, Walter E. Clark, William B. Howerton, G. M. Borgonovi, J. E. Hammelman, C. L. Miller, Robert P. Schuman, G. E. Bingham, B. R. Wheeler, Charles W. Forsberg, R. Strickert, A. M. Friedman, S. Fried, H. Thomas Blair, Allen S. Benjamin, David J. McCloskey, C. Plichon, R. Gueraud, M. H. Richli, J. F. Casagrande, Robert E. Buxbaum, Ernest F. Johnson, K. Subba Rao, M. Srinivasan, W. J. Lackey, R. E. Blanco, A. L. Lotts)
Demonstration of the Feasibility of Subsolidus Sintering of Radwaste-Containing SYNROC-B Composition(Ahmed G. Solomah, Thomas M. Hare, Hayne Palmour III)
Management, Stabilisation and Environmental Impact of Uranium Mill Tailings(John W. McKlveen)
Thermionic Converters and Low-Temperature Plasma(David T. Shaw)
MHD Instabilities(F. L. Cochran)
Superheavy Elements(Glenn T. Seaborg)

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

Number 3

Table of Contents
Authors(M. Cumo, G. E. Farello, J. Gasiorowski, G. Iovino, A. Naviglio, Kenzo Miya, Joseph Silverman, William G. Anderson, Richard P. Burke, Peter W. Huber, Ain A. Sonin, Richard P. Burke, Peter W. Huber, F. S. Gunnerson, A. W. Cronenberg, G. Breitbach, H. Barthels, Hashem Akbari, Lawrence M. Grossman, W. A. Woolson, M. L. Gritzner, R. Beraha, G. Beuken, G. Frejaville, C. Leuthrot, Y. Musante, William V. Macnabb, K. J. Hofstetter, W. B. Stroube, Jr., B. C. Henderson, G. A. Huff, R. W. Conn, F. Kantrowitz, W. F. Vogelsang, Alfred Chrubasik, Jürgen Hofmann, Horst Vietzke, B. Allard, G. W. Beall, T. Krajewski, Erik Kolstad, Gerhard Hofer, Chau Chun Hung, D. W. Kneff, Harry Farrar IV, F. M. Mann, R. E. Schenter, D. T. Bartlett, A. F. McKinlay, P. A. Smith)
Modem Formulas for Statics and Dynamics(Allan J. Malvick)
Storage of Spent Fuel Elements(Anthony Foderaro)
Energy Dictionary(James G. McCray)
Advances in Nuclear Physics(D. A. Bromley)