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Volume 51

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Number 1

Table of Contents
Authors(Sunanta Patrashakorn, Reiner Papp, G. Nash, A. Ghazanfari, E. F. Hicken, A. Ziegler, M. Kelm, B. Oser, S.Drobnik, W. D. Deckwer, Masaaki Uchida, Michio Ichikawa, Douglas W. Croucher, Jose L. Del Valle, Mujid S. Kazimi, Fred C. Schweppe, L. F. Hansen, C. Wong, T. T. Komoto, B. A. Pohl, R. J. Howerton, J. W. Behrens, R. A. Schrack, C. D. Bowman, Gad Shani, P. K. Job, M. Srinivasan, V. R. Nargundkar, N. H. Macmillan, R. Roy, P. T. B. Shaffer)
The Structure of World Energy Demand(Helmut J. Frank)
Advances in Nuclear Science and Technology(Clarence E. Lee)

Recycling of Actinides in Light Water Reactors

Sunanta Patrashakorn, Reiner Papp

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 7-12

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32550

An Appraisal of Subcooled Boiling and Slip Ratio from Measurements Made in the Lingen Boiling Water Reactor

G. Nash

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 13-20

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32551

Unsteady Dispersed Flow Heat Transfer Under Loss-of-Coolant Accident Related Conditions

A. Ghazanfari, E. F. Hicken, A. Ziegler

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 21-26

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32552

Denitration of Aqueous Waste Solutions from the Nuclear Fuel Reprocessing

M. Kelm, B. Oser, S. Drobnik, W. D. Deckwer

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 27-32

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT80-A32553

In-Pile Diameter Measurement of Light Water Reactor Test Fuel Rods for Assessment of Pellet-Cladding Mechanical Interaction

Masaaki Uchida, Michio Ichikawa

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 33-44

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32554

Behavior of Defective Pressurized Water Reactor Fuel Rods During Power Ramp and Power-Cooling-Mismatch Conditions

Douglas W. Croucher

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 45-57

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32555

A Comparison of Models for Electric Generation Planning

Jose L. Del Valle, Mujid S. Kazimi, Fred C. Schweppe

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 58-69

Technical Paper / Economic / dx.doi.org/10.13182/NT80-A32556

Measurements and Calculations of the Neutron Emission Spectra from Materials Used in Fusion-Fission Reactors

L. F. Hansen, C. Wong, T. T. Komoto, B. A. Pohl, R. J. Howerton

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 70-77

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32557

Nondestructive Examination of a Defective Silver Braze Using Resonance-Neutron Radiography

J. W. Behrens, R. A. Schrack, C. D. Bowman

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 78-82

Technical Paper / Analysis / dx.doi.org/10.13182/NT80-A32558

The Use of the Reaction ⁹³Nb(n,n')^93mNb for Fast Neutron Flux Measurement

Gad Shani

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 83-86

Technical Paper / Technique / dx.doi.org/10.13182/NT80-A32559

Analysis of the BeO-Reflected Uranium-233 Nitrate Solution Subcritical Multiplication Experiments Conducted at Purnima Laboratories

P. K. Job, M. Srinivasan, V. R. Nargundkar

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 87-96

Technical Note / Reactor / dx.doi.org/10.13182/NT80-A32560

Metal-Matrix Radioactive Waste Forms Prepared by Electrochemical/Gravity Co-Deposition

N. H. Macmillan, R. Roy, P. T. B. Shaffer

Nuclear Technology / Volume 51 / Number 1 / November 1980 / Pages 97-99

Technical Note / Radioactive Waste / dx.doi.org/10.13182/NT80-A32561

Number 2

Table of Contents
Authors(Don J. Bradley, G. L. McVay, C. Q. Buckwalter, G. H. Frischat, B. W. Veal, D. J. Lam, A. P. Paulikas, D. P. Karim, John N. Rosholt, Marcus N. Myers, Kathy A. Graff, J. Calvin Giddings, J. F. Relyea, Douglas P. Karim, P. Georgopoulos, G. S. Knapp, James V. Beitz, Jan P. Hessler, S. L. Ruby, Philip A. Helmke, P. C. Fung, G. W. Bird, N. S. McIntyre, G. G. Sanipelli, V. J. Lopata, Robert A. Zielinski, W. R. Waltz, W. L. Godfrey, A. K. Williams, Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare, George Emanuel, M. Roche, J. Morin, R. Musart, B. Pierre)
Preface: Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management(John P. Unik)
Alloy 800(O. Norman Carlson)
The Energy Center: New Alternative for Effective Energy Use(W. M. Beasley)
Nuclear Power Plant Engineering(Kermit L. Garlid)
Radiation Protection—Progress Report 1978(Geoffrey G. Eichholz)

Basic Research for Evaluating Nuclear Waste Form Performance

Don J. Bradley

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 111-122

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32589

The Nature of Glass Leaching

G. L. McVay, C. Q. Buckwalter

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 123-129

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32590

Self-Diffusion Processes in Oxide Glasses

G. H. Frischat

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 130-135

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32591

X-Ray Photoelectron Spectroscopy Studies of Silicate Glasses: Implications to Bonding and Leaching

B. W. Veal, D. J. Lam, A. P. Paulikas, D. P. Karim

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 136-142

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32592

Uranium and Thorium Disequilibrium in Zeolitically Altered Rock

John N. Rosholt

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 143-146

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32593

Application of Field-Flow Fractionation to Radioactive Waste Disposal

Marcus N. Myers, Kathy A. Graff, J. Calvin Giddings

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 147-155

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32594

Diffusion Coefficients and Their Use

J. F. Relyea

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 156-161

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32595

Extended X-Ray Absorption Fine Structure Studies of Actinide Ions in Aqueous Solution

Douglas P. Karim, P. Georgopoulos, G. S. Knapp

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 162-168

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32596

Oxidation State Specific Detection of Transuranic Ions in Solution

James V. Beitz, Jan P. Hessler

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 169-177

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel Cycle / dx.doi.org/10.13182/NT80-A32597

Possible Applications of the Mössbauer Technique in Waste Management Studies

S. L. Ruby

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 178-181

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32598

Rock Alteration and Mineral Transformations for Nuclear Waste Management

Philip A. Helmke

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 182-187

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32599

Aspects of Feldspar Dissolution

P. C. Fung, G. W. Bird, N. S. Mcintyre, G. G. Sanipelli, V. J. Lopata

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 188-196

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32600

Stability of Glass in the Geologic Environment: Some Evidence from Studies of Natural Silicate Glasses

Robert A. Zielinski

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 197-200

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste / dx.doi.org/10.13182/NT80-A32601

Summary: Workshop Recommendations—Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management

A. M. Friedman, D. J. Lam, M. G. Seitz

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 201-202

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / dx.doi.org/10.13182/NT80-A32602

Fuel Cycle Utilizing Plutonium-238 as a“Heat Spike” for Proliferation Resistance

W. R. Waltz, W. L. Godfrey, A. K. Williams

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 203-216

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel Cycle / dx.doi.org/10.13182/NT80-A32603

Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel

Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 217-237

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel / dx.doi.org/10.13182/NT80-A32604

Cascade Performance for Large Separation Factors

George Emanuel*

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 238-243

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Isotopes Separation / dx.doi.org/10.13182/NT80-A32605

A New Neutron Detection Technique: Fissile Resistors

M. Roche, J. Morin, R. Musart, B. Pierre

Nuclear Technology / Volume 51 / Number 2 / December 1980 / Pages 244-258

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Technique / dx.doi.org/10.13182/NT80-A32606

Number 3

Table of Contents
Authors(Stanley H. Fistedis, James M. Kennedy, Ted B. Belytschko, Daniel F. Schoeberle, Henry J. Petroski, John L. Glazik, Jr., Chung-Yi Wang, James M. Kennedy, Han Y. Chu, Ronald F. Kulak, Yao W. Chang, Joseph Gvildys, Chung-Yi Wang, Ronald F. Kulak, Wayne R. Zeuch, Chung-Yi Wang, Algirdas H. Marchertas, Ted B. Belytschko, Ralph W. Seidensticker, Algirdas H. Marchertas, Zdeněk P. Bažant, M. T. A-Moneim, Wayne R. Zeuch, Ralph W. Seidensticker, Howard L. Schreyer)
Preface: Mechanics Applications to Fast Breeder Reactor Safety(Stanley H. Fistedis)

Characterization of Liquid-Metal Fast Breeder Reactor Engineering Mechanics Effort by Lines-of-Assurance

Stanley H. Fistedis

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 271-289

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32567

A Quasi-Eulerian Fluid-Structure Code for Simulation of High-Pressure Transients in Core Components

James M. Kennedy, Ted B. Belytschko, Daniel F. Schoeberle

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 290-302

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32568

Effects of Cracks on the Response of Circular Cylindrical Shells

Henry J. Petroski, John L. Glazik, Jr.

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 303-316

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32569

The Dynamic Response of Cracked Fast Reactor Subassembly Ducts

John L. Glazik, Jr., Henry J. Petroski

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 317-331

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32570

A Eulerian Method for Analyzing Above-Core Hydrodynamics and Sodium Spillage During a Hypothetical Core Disruptive Accident

Chung-Yi Wang

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 332-348

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32571

Three-Dimensional Nonlinear Structural Model for Above-Core Structures

James M. Kennedy

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 349-362

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32572

Arbitrary Lagrangian-Eulerian Method for Transient Fluid-Structure Interactions

Han Y. Chu

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 363-377

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32573

Theory and Application of Three-Dimensional Treatment of Pool-Type Liquid-Metal Fast Breeder Reactor Components

Ronald F. Kulak

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 378-387

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32574

Validation of Primary Containment Computer Codes

Yao W. Chang, Joseph Gvildys

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 388-399

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32575

Analysis of High-Energy Excursions Using the Implicit Continuous-Fluid Eulerian Containment Code (ICECO)

Chung-Yi Wang

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 400-413

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32576

Three-Dimensional Analysis of Reactor Decks and Their Supports

Ronald F. Kulak

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 414-420

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32577

Analysis of Sodium Spillage from Primary Containment Following Slug Impact

Wayne R. Zeuch, Chung-Yi Wang

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 421-432

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32578

Transient Analysis of a Prestressed Concrete Reactor Vessel for Liquid-Metal Fast Breeder Reactor Primary Containment

Algirdas H. Marchertas, Ted B. Belytschko

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 433-442

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32579

Increasing Primary Containment Capabilities of Liquid-Metal Fast Breeder Reactor Plants by the Use of Prestressed Concrete

Ralph W. Seidensticker, Algirdas H. Marchertas, Zdeněk P. Bažant

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 443-451

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32580

Recent Applications and Improvements of the Hydrodynamic-Structural Piping Code ICEPEL

M. T. A-Moneim

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 452-463

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32581

Three-Dimensional Finite Element Formulation for Elastic-Plastic Nonlinear Analysis of Piping Systems

M. T. A-Moneim

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 464-475

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32582

Events Contributing to Internal Loading of Secondary Containment: An Integrated Approach

Wayne R. Zeuch

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 476-488

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32583

Potential Advantages of Prestressed Concrete for Liquid-Metal Fast Breeder Reactor Secondary Containment

Ralph W. Seidensticker, Howard L. Schreyer

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 489-498

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32584

Perspective: Mechanics Applications to Fast Breeder Reactor Safety

Stanley H. Fistedis

Nuclear Technology / Volume 51 / Number 3 / December 1980 / Pages 499-500

Technical Paper / Mechanics Applications to Fast Breeder Reactor Safety / dx.doi.org/10.13182/NT80-A32585