Home / Publications / Journals / Nuclear Technology / Volume 56 / Number 2

Volume 56

Number 2

Table of Contents
Authors(D. E. Clark, L. Urwongse, C. Maurer, David G. Coles, Fernando Bazan, L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine, R. P. Schuman, Joseph H. Simmons, Aaron Barkatt, Pedro B. Macedo, Aaron Barkatt, Alisa Barkatt, Pehr E. Pehrsson, Pedro B. Macedo, Joseph H. Simmons, C. R. Kennedy, K. F. Flynn, R. M. Arons, J. T. Dusek, Barry E. Scheetz, William B. White, Scott D. Atkinson, Claudio Pescatore, Albert J. Machiels, B. A. Staples, B. E. Paige, D. W. Rhodes, M. W. Wilding, D. M. Strachan, R. P. Turcotte, B. O. Barnes, P. A. Pizzica, H. H. Hummel, R. J. LaBauve, T. R. England, D. C. George, C. W. Maynard, R. E. Williford, D. D. Lanning, C. L. Mohr, A. Knoll, A. Notea, Y. Segal, J. O. Blomeke, A. G. Croff, Seyyed Nejat, Nicholas Tsoulfanidis, Robert C. Sanders, H. G. Groehn, Vikram N. Patel, J. N. Anno)
Preface: Comparative Leaching Behavior of Radioactive Waste Forms(Martin G. Seitz)
Overview: Argonne Workshop on Comparative Leaching Behavior of Radioactive Waste Forms(A. M. Friedman)
Thermal Analysis of Pressurized Water Reactors(K. Almenas)
Physics of Modern Materials (Vols. I and II)(J. C. Corelli)
Nuclear Disaster in the Urals(Dennis D. Patton)
Two-Phase Flow and Heat Transfer in the Power and Process Industries(Gary A. Pertmer)
Theory of the Nuclear Shell Model(D. A. Bromley)
Basic Elements of Light Water Reactor Fuel Rod Design(Joel Weisman, Roy Eckart)

Application of Glass Corrosion Concepts to Nuclear Waste Immobilization

D. E. Clark, L. Urwongse, C. Maurer

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 212-225

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32849

Continuous-Flow Leaching Studies of Crushed and Cored SYNROC

David G. Coles, Fernando Bazan

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 226-237

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32850

Mechanisms of Leaching and Dissolution of UO₂ Fuel

L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 238-253

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32851

Leach Testing of Idaho Chemical Processing Plant Final Waste Forms

R. P. Schuman

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 254-264

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32852

Mechanisms That Control Aqueous Leaching of Nuclear Waste Glass

Joseph H. Simmons, Aaron Barkatt, Pedro B. Macedo

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 265-270

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32853

The Importance of CO₂ Buffering and of the Total Ionic Balance in Measurements on the Durability of Glasses

Aaron Barkatt, Alisa Barkatt, Pehr E. Pehrsson, Pedro B. Macedo, Joseph H. Simmons

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 271-277

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32854

Comparative Leaching Behavior of SYNROC B and A Borosilicate Glass

C.R. Kennedy, K. F. Flynn, R. M. Arons, J. T. Dusek

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 278-288

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32855

Dissolution of Aluminum-, Titanium-, and Zirconium-Based Crystalline Waste Form Components Under Hydrothermal Conditions

Barry E. Scheetz, William B. White, Scott D. Atkinson

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 289-296

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32856

A Criterion for Selecting Leach Test Specimen Sizes

Claudio Pescatore, Albert J. Machiels

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 297-300

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32857

Leaching Properties and Chemical Composition of Calcines Produced at the Idaho Chemical Processing Plant

B.A. Staples, B. E. Paige, D. W. Rhodes, M. W. Wilding

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 301-305

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32858

MCC-1: A Standard Leach Test for Nuclear Waste Forms

D.M. Strachan, R. P. Turcotte, B. O. Barnes

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 306-309

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32859

The Effect of Time Delays in Fuel Pin Failure on LOF-TOP Transient Calculations for a Commercial-Sized LMFBR

P. A. Pizzica, H. H. Hummel

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 313-321

Nuclear Safety / dx.doi.org/10.13182/NT82-A32860

Fission Product Analytic Impulse Source Functions

R. J. LaBauve, T. R. England, D. C. George, C. W. Maynard

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 322-339

Fuel Cycle / dx.doi.org/10.13182/NT82-A32861

A Model for the Effective Thermal and Mechanical Properties of Cracked UO₂ Pellets

R. E. Williford, D. D. Lanning, C. L. Mohr

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 340-350

Nuclear Fuel / dx.doi.org/10.13182/NT82-A32862

Probabilistic Interpretation of Nuclear Waste Assay by Passive Gamma Technique

A. Knoll, A. Notea, Y. Segal

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 351-360

Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32863

Nuclear Waste Partitioning and Transmutation

J. O. Blomeke, A. G. Croff

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 361-371

Radioactive Waste Management / dx.doi.org/10.13182/NT82-A32864

The Effect of Plant Reliability Improvement in the Cost of Generating Electricity

Seyyed Nejat, Nicholas Tsoulfanidis, Robert C. Sanders

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 372-391

Economic / dx.doi.org/10.13182/NT82-A32865

Estimate of Cross Flow in High Temperature Gas-Cooled Reactor Fuel Blocks

H. G. Groehn

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 392-400

Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A32866

Radiation-Induced Outgassing from Sorption Pump Material

Vikram N. Patel, J. N. Anno

Nuclear Technology / Volume 56 / Number 2 / February 1982 / Page 401

Technical Note / Material / dx.doi.org/10.13182/NT82-A32867