ADVANCES IN CERAMICS • VOLUME 20

NUCLEAR WASTE MANAGEMENT II

Edited by

D. E. Clark University of Florida Department of Materials Science and Engineering Gainesville, Florida

W. B. White The Pennsylvania State University Materials Research Laboratory University Park, Pennsylvania

A. J. Machiels Electric Power Research Institute Box 10412 Palo Alto, California

The American Ceramic Society, Inc. Westerville, Ohio

Contents

SECTION I. WASTE GENERATION AND MANAGEMENT

U.S. Defense High-Level Waste Program 3 R. D. Walton Jr., A. L. Taboas, and S. P. Cowan

Role of the MRS in the High-Level Radioactive Waste Management System 9

J. R. Hilley

Regulatory Research on Materials Used for Nuclear Waste Management—Update 17

K. S. Kim

Effect of Nuclear Waste Policy Act of 1982— Three Years Later 29

E. J. Hennelly

SECTION II. WASTE FORM PROCESSING AND REPOSITORY TEST PROGRAMS

The Defense Waste Processing Facility: The Vitrification of High-Level Nuclear Waste 37

W. J. Brumley

Technology for the Long-Term Management of Defense HLW at the Idaho Chemical Processing Plant 45

B. A. Staples, J. R. Berreth, and D. A. Knecht

Test Methods for Selection of Materials of Construction for High-Level Radioactive Waste Vitrification 53

D. F. Bickford, R. A. Corbett, and W. S. Morrison

High-Temperature Materials for Radioactive Waste Incineration and Vitrification 65

D. F. Bickford, R. S. Ondrejcin, and L. Salley

Overview of the Waste/Barrier/Rock Interactions Testing Program of the Basalt Waste Isolation Project 79

P. F. Salter, J. R. Burnell, and D. L. Lane

Estimates of Radionuclide Release from Glass Waste Forms in a Tuff Repository and the Effects on Regulatory Compliance 91

R. D. Aines

Overview of Waste Package Performance Experiments in WIPP 99

M. A. Molecke

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SECTION III. GLASS WASTE FORMS

Present Status of the French Continuous Fission Product Vitrification Process 105

A. Jouan, C. Ladirat, and J. P. Moncouyoux

Rheology of Glasses Containing Crystalline Material 117 M. J. Plodinec

Oxygen Diffusion in SRL Waste Glass Melts 125 H. D. Schreiber, S. J. Kozak, B. D. Trandel, and C. W. Schreiber

TEM Observation of the Crystallization Behavior of a Complex Ferrisilicate a-Waste Glass 133

A. D. Stalios, P. Delavignette, and R. De Batist

Hydrolytic Durability of Lead-Iron-Phosphate Glasses 141 L. Kahl

Evaluation of Lead-Iron-Phosphate Glass As a High-Level Waste Form 149

L. A. Chick, L. R. Bunnell, D. M. Strachan, H. E. Kissinger, and F. N. Hodges

Investigation of Lead-Iron-Phosphate Glass for SRP Waste . . . 157 C M . Jantzen

High-Temperature Glasses for Nuclear Waste Isolation 167 L. R. Bunnell, G. D. Maupin, and K. H. Oma

An Accurate Simulation of Radiation Damage in a Nuclear Waste Repository 175

J. P. Heuer, H. W. Chan, D. G. Howitt, and J. F. DeNatale

Effect of Heat Pretreatment on Foaming of Simulated Nuclear Waste in a Borosilicate Glassmeltt 181

J. S. Ahn and P. Hrma

Resolution-Enhanced Reflectance Spectroscopy of Nuclear Waste Glass 191

B. K. Zoitos and D. E. Clark

SECTION IV. CERAMIC WASTE FORMS

Low-Temperature Materials for Waste Disposal: I, Hydroxylated Phases 199

S. Komarneni and R. Roy

Cesium Exchange, Selectivity, and Fixation Properties of y-Titanium Phosphate 207

S. Komarneni and R. Roy

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Influence of Heat Treatment and Redox Conditions on Crystallization of Titanosilicate Glass-Ceramics 215

P. J. Hayward, E. R. Vance, C. D. Cann, and I. M. George

Leaching Mechanisms in Polyphase Ceramic High-Level Nuclear Waste Forms 223

A. B. Harker and W. B. White

Dissolution of Sphene and Sphene Glass-Ceramics in Aqueous Media 231

E. R. Vance

Progress in Development of a Source Term for Sphene Glass-Ceramic Dissolution under Vault Conditions 241

P. J. Hayward, J. C. Tait, I. M. George, A. A. Carmichael, and J. P. M. Ross

Immobilization of Uranium-Rich High-Level Nuclear Waste . . . . 249 E. R. Vance, S. Urquhart, D. Anderson, and I. M. George

Immobilization of Uranium-Rich High-Level Radioactive Liquid Waste in Synroc-FA 259

A. G. Solomah, T. S. Sridhar, and S. C. Jones

Fixation of HAW and TRU Waste in a Ceramic Matrix via a Sol-Gel Process 267

E. Zimmer

SECTION V: CEMENTS AND GROUTS

Effects of Phase Composition on the Strontium Leachability of Cement-Based Waste Forms 275

S. Hoyle and M. W. Grutzeck

Cement Encapsulation of Uranyl Nitrate Waste 285 D. C. Grant, E. E. Smeltzer, M. C. Skriba, S. A. Coolidge, J. C. Cwynar, and L. Eisenstatt

Empirical Equatlon for Statistical Analysis of Waste Grout Data 297

O. K. Tallent, E. W. McDaniel, and T. T. Godsey

Testing Protocols for Evaluating Monolithic Waste Forms Containing Mixed Waste 305

T. M. Gilliam, T. L. Sams, and W. W. Pitt

The Effect of Chemically Adjusting Cement Compositions on Leachabilities of Waste Ions 313

M. W. Barnes, B. E. Scheetz, and D. M. Roy

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SECTION VI: CONTAINERS AND SPENT FUEL

Ceramic Containers for Spent Nuclear Fuel: On the Corrosion Resistance of Rutile 321

S. Forberg

Gamma Radiolysis Effects on Leaching Behavior of Ceramic Materials for Nuclear Fuel Waste Immobilization Containers.. . 329

M. Onofrei, D. K. Raine, W. H. Hocking, K. George, and J. S. Betteridge

Corrosion Phase Formation on Container Alloys in Basalt Repository Environments 341

R. G. Johnston, R. P. Anantatmula, J. M. Lutton, and C. L. Rivera

Experimental Investigations of the Long-Term Performance of Spent Fuel Waste Forms 351

S. L. Nicolosi and J. L. Means

Initial Hydrothermal Waste Package Release Experiments Using Spent Fuel with Waste Package Components 361

J. R. Burneil, D. G. Coles, and L. E. Thomas

SECTION VII: WEST VALLEY WASTE MANAGEMENT PROGRAM

West Valley: Implementing Modern Waste Technology 375 J. L. Knabenschuh, W. H. Hannum, and T. W. Mclntosh

Zeolite Variability in the WVDP HLW Glass Feed Streams 383 D. E. Carl. L. E. Rykken, J. R. Stimmel, J. H. Marlow, L. A. Bray, and B. M. Wise

The West Valley Vitrification Process Model: A Method for Providing Glass Composition 391

L. R. Eisenstatt and N. E. Chapman

Chemical Determination of West Valley Waste Form Products 399

D. M. Oldman, J. H. Marlow, and J. R. Stimmel

Control and Data Acquisition for a Slurry-Fed Ceramic Melter System for High-Level Nuclear Waste 407

V. C. Drankhan, N. E. Chapman, and J. M. Pope

Results from Functional Checkout of the Vitrification Process at the West Valley Demonstration Project 413

T. F. Murawski, S. M. Barnes, L. L. Petkus, and C. C. Chapman

Field Verification of Radioactive Waste Form Development Testing 421

P. M. Petrone, J. C. Cwynar, D. C. Grant, and E. E. Smeltzer

SECTION VIII: LEACHING—MODELS AND MECHANICS

Dissolution Mechanisms of Nuclear Glasses: A Critical Review 431

W. B. White

Corrosion Rate of Nuclear Glass in Saturated Media 443 S. Fillet, E. Vernaz, J. L. Nogues, and N. Jacquet-Francillon

Effects of SA/V and Saturation on the Chemical Durability of SRP Waste Glass 455

G. T. Chandler, G. G. Wicks, and R. M. Wallace

Reaction of Nuclear Waste Glass with Slowly Flowing Solutions 465

B. Grambow, H. P. Hermansson, I. K. Björner, H. Christensen, and L. Werme

Leaching of Simulated Nuclear Waste Glass under Dynamic Conditions 475

H. Christensen, H. P. Hermansson, I. K. Björner, and T. Ohe

Leach Behavior of a Defense Waste Glass Under Static and Dynamic Conditions 487

R. Adiga, Aa. Barkatt, and D. E. Clark

The Dissolution of a Glass Having an Adherent Insoluble Surface Layer 495

K. B. Harvey and C. A. Boase

The Role of Colloid Formation on Waste Glass Leaching and Surface Layer Formation 505

C. T. Lee and D. E. Clark

Glass-Water Vapor Interaction 515 F. E. Diebold and J. K. Bates

A Leach Model for Safety Assessment 523 H. Umeki, A. Suzuki, and R. Kiyose

Progress Report on Experimental Evaluation of a Nuclear Waste Glass Corrosion Model 531

E. D. Spinoza and J. L. Means

Effects of Solution Cations on Waste Glass Leaching 541 C. T. Lee and D. E. Clark

Design and Use of a Sealed Radioactive Leach Test Apparatus 551

M. C. Arneson, C. A. Boase, K. W. Chambers, E. M. Gardy, and K. B. Harvey

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SECTION IX: SYSTEMS AND FIELD TESTS

Field Burial Results and SIMS Analysis of the Chalk River Glass Blocks 559

J. C. Tait, W. H. Hocking, J. S. Betteridge, and G. Bart

SIMS Analysis of Leached Layers Formed on SRL Glasses During Burial 567

A. R. Lodding, E. U. Engström, D. E. Clark, L. O. Werme, and G. G. Wicks

Stripa Burial: Time Dependence of Leaching 583 L. L. Hench, B. F. Zhu, A. R. Lodding, and L. Werme

Two-Year Leaching Behavior of Three SRL Nuclear Waste Glasses in Granite 591

B. F. Zhu, D. E. Clark, A. R. Lodding, and G. G. Wicks

Radiocolloid Formation in Waste Package Leach Tests with Savannah River Defense Waste Glass in Salt Brine 601

B. P. McGrail

The Effect of Gamma Radiation on Ground-Water Chemistry and Glass Leaching as Related to the NNWSI Repository S i te . . 609

T. Abrajano, J. Bates, W. Ebert, and T. Gerding

Leaching Fully Radioactive SRP Nuclear Waste Glass in Tuff Ground Water in Stainless Steel Vessels 619

N. E. Bibler

The Interaction between Nuclear Waste Glasses and Clay 627 P. Van Iseghem, R. DeBatist, and Li Wei-Yin

Analysis of Spent-Fuel Performance in a Geologie Repository.. 639 M. J. Apted, A. M. Liebetrau, and D. W. Engel

In-Situ Testing of Nuclear Waste Forms in an Underground Laboratory in Clay 649

P. Van Iseghem, W. Timmermans, W. Debruyn, J. Dresselaers, and B. Neerdael

WIPP/SRL In-Situ Testing Program 657 G. G. Wicks and M. A. Molecke

SECTION X: NATURAL ANALOGS—THEIR RELEVANCE IN PREDICTING LONG-TERM WASTE FORM STABILITY

Alteration Products of Basalt Glass from Frenchman Springs Flow, Wanapum Basalts, Hanford, Washington 671

M. J. Jercinovic, R. C. Ewing, and C. D. Byers

XII

Leaching of Microtektite Glass Compositions in Seawater 681 Aa. Barkatt, E. E. Saad, R. Adiga, W. Sousanpour, AI. Barkatt, and S. Alterescu

The Corrosion of Tektite Glass 689 J. A. O'Keefe

Natural Glasses in Howardites and Chondrites (Meteorites) . . . . 693 L. C. Klein

Hydration of High-Silica Glasses in the Deep Sea 699 A. N. Federman

Prediction of Nuclear Waste Glass Durability from Natural Analogs 703

C M . Jantzen

Surface Reactions of Natural Glasses; Effects on Radionuclide Transport 713

A. F. White

Solution of Natural Glasses in the Geological Environment . . . . 723 B. P. Glass

Experimental Alteration of Basalt Glass Applied to the Alteration of Nuclear Waste Glass 733

C. D. Byers, R. C. Ewing, and M. J. Jercinovic

X-Ray Powder Diffraction Analysis of Alpha-Event Radiation Damage in Zircon (ZrSi04) 745

T. Murakami, B. C. Chakoumakos, and R. C. Ewing

Icelandic Geothermal Fields as an Analog for Nuclear Waste Disposal in Basalt 755

G. C. Ulmer, G. H. Kacandes, and D. E. Grandstaff

Author Index 765

Subject Index 769

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