Glass as a waste form and vitrification technology : summary of an international workshop / Steering Committee on Vitrification of Radioactive Wastes, Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council.

Format:

Book

Contributor:

National Research Council (U.S.). Steering Committee on Vitrification of Radioactive Wastes.

Language:

English

Subjects (All):

Radioactive wastes--Vitrification--Congresses.

Radioactive wastes.

Physical Description:

1 online resource (172 p.)

Edition:

1st ed.

Place of Publication:

Washington, D.C. : National Academy Press, 1996.

Language Note:

English

Contents:

Glass as a Waste Form and Vitrification Technology: Summary of an International Workshop

Copyright

Preface

Contents

Executive Summary

1 Introduction

ORGANIZATION OF THE WORKSHOP

HISTORY

THE U.S. PROGRAM

2 Three "Futures" for Glass

FUTURE 1: THE ONLY BARRIER TO LONG-TERM RELEASE

Science

Technology

FUTURE 2: AN EFFECTIVE, BUT NOT NECESSARILY THE PRIMARY BARRIER TO LONG-TERM RELEASE

FUTURE 3: A TOTALLY INEFFECTIVE BARRIER TO LONG-TERM RELEASE

3 Special Applications of Glass

4 Conclusions

STATE OF KNOWLEDGE OF THE SCIENCE

STATE OF PRACTICE OF THE TECHNOLOGY

FUTURE WASTE FORMS

References

Appendix A Biographical Sketches of Steering Committee Members

Appendix B Workshop Program

Appendix C List of Workshop Participants

AUSTRALIA

BELARUS

BELGIUM

CANADA

CHINA

CZECH REPUBLIC

FRANCE

GERMANY

JAPAN

KOREA

RUSSIA

SWEDEN

UNITED KINGDOM

UNITED STATES

NRC STAFF

Appendix D Identification and Summary of Characterization of Materials Potentially Requiring Vitrification

PREFACE

1. Civilian Light-Water-Reactor Spent Fuel

Genesis

Description

2. DOE-Responsibility Spent Fuels

3. DOE ''Tank'' Wastes

4. Capsules of Separated Radiocesium and Radiostrontium

5. Transuranic Wastes

6. Low-Level Radioactive Wastes

7. Low-Level Mixed Wastes

8. Surplus Plutonium

9. DOE Environmental Restoration Wastes

Appendix E Abstracts of Invited Workshop and Poster Presentations

Vitrification of Radioactive Waste: Past Accomplishments and Future Challenges

Abstract.

References

OVERVIEW OF CURRENT DOE PLANS AND ACTIVITIES INVOLVING VITRIFICATION

IDENTIFICATION AND SUMMARY CHARACTERIZATION OF MATERIALS POTENTIALLYREQUIRING VITRIFICATION

Hanford Wastes and Glass Composition

ACCEPTANCE OF WASTE FOR DISPOSAL IN THE POTENTIAL UNTIED STATES REPOSITORY AT YUCCA MOUNTAIN, NEVADA

INTRODUCTION

WASTE ACCEPTANCE

SUMMARY

A Review of Status of Science of Vitrified Waste Form Development

Leach Tests and Chemical Durability

References:

Status of Vitrification Technologies

ABSTRACT

THE CHEMISTRY AND KINETICS OF WASTE GLASS CORROSION

REFERENCES

Waste Glass Leaching and Long-Term Modeling

Waste Glass Leaching and Long-Term Durability

Corrosion Behavior of Glass: Remaining Scientific Issues

(1) General glass dissolution phenomena

(2) Behavior of safety relevant radionuclides during glass dissolution

NATURAL GLASSES AND THE VERIFICATION OF THE LONG-TERM DURABILITY OF NUCLEAR WASTE GLASSES

Selected References

Actinide Vitrification: Status of Savannah River Site Activities

Thermal Stability of Waste Form Glass

MECHANICAL PROPERTIES OF THE WASTE FORM GLASS

Abstract

Radiation Effects in Glass Waste Forms

Review of Radiation Effects

DOE Panel Findings

EXPERIENCE IN BELGIUM

Operational experience of the Pamela Facility

Quality Assurance Programme

Recommendations for future Vitrification.

Key-References

VITRIFICATION EXPERIENCE IN FRANCE - DEVELOPMENT AND PERSPECTIVES

EXPERIENCE IN THE UNITED STATES: WEST VALLEY, NEW YORK

Introduction

High-level Waste Pretreatment and Consolidation

High-level Waste Vitrification Activities

Conclusion

Vitrification Experience of TVF in Japan

Vitrification Experience in the UK

Reference.

Experiences with Vitrification HLW and Development of New Approaches in Russia

Vitrification Experience in China

COMPOSITION OF HLLW

GLASS FRIT AND GLASS PRODUCT

VITRIFICATION PROCESS

Feed Preparation

Vitrification

Off Gas Treatment

Canister Handling

FEATURES OF FACILITY

Melter Cell

Melter

TEST OF MELETER

Vitrification Experience at the Defense Waste Processing Facility (DWPF)

Natural Glasses as Analogs for Nuclear Waste Glasses

ALTERATION OF NUCLEAR WASTE GLASSES CHARACTERIZED BY RADON EMANATION METHOD

PRINCIPLE OF THE RADON EMANATION METHOD (REM) AND PREPARATION OFSAMPLES

RESULTS AND DISCUSSION

CONCLUSIONS

ACKNOWLEDGMENTS

DOE REGULATORY INITIATIVE FOR VITRIFIED MIXED WASTE

Background

DOE's Regulatory, Initiative

Basis for Initiative

Regulatory Control

Waste Form Testing Strategy

Summary and Conclusion

Acknowledgments

Stabilization of Plutonium in Hybrid Glass Materials Using a Cyclone Melter

Extended Abstract

DOE REGULATORY INITIATIVE: IMMOBILIZED MIXED DEBRIS

DOE'S PROPOSAL

Integrity of the Final Waste Form

Proposed Encapsulants

Risk-Based Analysis of Low-Level Disposal Facilities

Reexamination of Variables Affecting the Hydration of Obsidians Using Empirical Chronological Data and Laboratory Induced Hyd

Statistical Analysis

REFERENCES CITED:

A PLASMA ARC - VITREOUS CERAMIC PROCESS FOR HAZARDOUS AND RADIOACTIVE WASTE STABILIZATION

DIRECT CONVERSION OF METALS, CERAMICS, AMORPHOUS SOLIDS, HALOGENS, AND ORGANICS TO BOROSILICATE GLASS USING THE GMODS PROCESS

GMODS PROCESS DESCRIPTION

STATUS OF LABORATORY WORK

REFERENCES.

SURFACE LAYER FORMATION OF THE FRENCH SON68 NUCLEAR WASTE GLASS DURING VAPOR PHASE ALTERATION AT 200°C

POTENTIAL APPLICATION OF ELECTRON SPIN RESONANCE TO THE STUDY OF RADIATION EFFECTS IN HIGH-LEVEL NUCLEAR WASTE DISPOSAL GLASS

LEACHING BEHAVIOR OF PU AND CM FROM WASTE GLASS UNDER REDUCING CONDITION

Glass and Glass-Ceramic Waste Forms Developed at the Idaho Chemical Processing Plant for Immobilizing HLW and Actinides

REPRODUCTION OF NATURAL CORROSION BY ACCELERATED LABORATORY TESTINGMETHODS

Vapor Hydration Tests on Tektite and Obsidian Glasses

Nine-Year Results from Testing Basaltic and Simulated Waste Glasses

COLLOID FORMATION DURING WASTE GLASS CORROSION

Use Of DC Graphite Arc Melter Technology For Production Of Stable Vitrified Waste Forms

Hanford Low Level Waste Melter Tests

Experimental Determination of Uranium Oxide Solubility in Hydrous Silicate Melts of Granitic Composition

Mixture Models Versus Free Energy of Hydration Models for Waste Glass Durability

MICROSTRUCTURES AND LEACH RATES OF GLASS-CERAMIC WASTE FORMS FORIMMOBILIZING PLUTONIUM AND ASSOCIATED COMPONENTS

Vitrification Under Pressure

Vitrification In Ambient Atmosphere

HOT ISOSTATIC PRESS (HIP) VITRIFICATION OF RADWASTE CONCRETES

Reference:

Waste Glass Leaching During Open Site Tests

EXPERIMENTS AND RESULTS

In Situ Vitrification of Plutonium and Uranium Contaminated Buried Wastes: Microcompositional Analyses of Vitreous and...

ISV Process

Demonstrations on Plutonium and Uranium Contaminated Buried Wastes

THE INTERACTION BETWEEN HLW GLASS AND CLAY: PRESENT STATUS AND FUTUREPROGRAMME.

VERIFICATION STUDIES ON THE PAMELA HIGH-LEVEL WASTE GLASSES

Synroc - an Alternative Waste Form.

CHEMISTRY OF IRRADIATED SOLIDS

CORALUS: IN - SITU CORROSION TEST ON ACTIVE HLW GLASS

1. Objectives

2. Work Content

Notes:

Bibliographic Level Mode of Issuance: Monograph

Includes bibliographical references.

ISBN:

1-280-19180-5

9786610191802

0-309-59007-8

0-585-08445-9

OCLC:

44962772