Durability of Zirconium-Containing Ceramic Waste Forms in Water

The durability of three ceramic waste forms containing Zr as a constituent is examined at 90° and 150°C in HCl or deionized water. The three ceramic waste forms examined are: (A) 10‐mol%‐Y2O3‐stabilized ZrO2, (B) La2Zr2O7 with a pyrochlore structure, and (C) CaZrO3 with a perovskite structure. Each...

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Veröffentlicht in:Journal of the American Ceramic Society 1991-04, Vol.74 (4), p.863-864
Hauptverfasser: Kamizono, Hiroshi, Hayakawa, Issei, Muraoka, Susumu
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container_title Journal of the American Ceramic Society
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creator Kamizono, Hiroshi
Hayakawa, Issei
Muraoka, Susumu
description The durability of three ceramic waste forms containing Zr as a constituent is examined at 90° and 150°C in HCl or deionized water. The three ceramic waste forms examined are: (A) 10‐mol%‐Y2O3‐stabilized ZrO2, (B) La2Zr2O7 with a pyrochlore structure, and (C) CaZrO3 with a perovskite structure. Each form contains an appropriate amount of Ce, Nd, and Sr to simulate the leaching behavior of actinides, lanthanides, and alkaline‐earth fission products from highlevel nuclear waste. Two forms, (A) 10‐mol%‐Y2O3‐stabilized ZrO2 and (B) La2Zr2O7 with a pyrochlore structure, show excellent durability in HCl and deionized water. For example, leach rates of all constituents in the La2Zr2O7 waste form are less than about 10−4 g·m−2·d−1 at 150°C for a leach time of 32 d in deionized water.
doi_str_mv 10.1111/j.1151-2916.1991.tb06942.x
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Ceramics. Glasses</topic><topic>Ceramic industries</topic><topic>CERAMICS</topic><topic>CHALCOGENIDES</topic><topic>CHEMICAL COMPOSITION</topic><topic>Chemical industry and chemicals</topic><topic>CHEMICAL PROPERTIES</topic><topic>CHLORINE COMPOUNDS</topic><topic>durability</topic><topic>Exact sciences and technology</topic><topic>geology</topic><topic>HALOGEN COMPOUNDS</topic><topic>HIGH-LEVEL RADIOACTIVE WASTES</topic><topic>HYDROCHLORIC ACID</topic><topic>HYDROGEN COMPOUNDS</topic><topic>INORGANIC ACIDS</topic><topic>Key words</topic><topic>MANAGEMENT</topic><topic>MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</topic><topic>MATERIALS</topic><topic>MATERIALS SCIENCE</topic><topic>MECHANICAL PROPERTIES</topic><topic>Miscellaneous</topic><topic>nuclear waste</topic><topic>OXIDES</topic><topic>OXYGEN COMPOUNDS</topic><topic>RADIOACTIVE MATERIALS</topic><topic>RADIOACTIVE WASTE DISPOSAL</topic><topic>RADIOACTIVE WASTE MANAGEMENT</topic><topic>RADIOACTIVE WASTES</topic><topic>Technical ceramics</topic><topic>TRANSITION ELEMENT COMPOUNDS</topic><topic>WASTE DISPOSAL</topic><topic>WASTE FORMS</topic><topic>WASTE MANAGEMENT</topic><topic>WASTES</topic><topic>WATER</topic><topic>zirconium</topic><topic>ZIRCONIUM COMPOUNDS</topic><topic>ZIRCONIUM OXIDES</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kamizono, Hiroshi</creatorcontrib><creatorcontrib>Hayakawa, Issei</creatorcontrib><creatorcontrib>Muraoka, Susumu</creatorcontrib><collection>Istex</collection><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Technology Research Database</collection><collection>Materials Research Database</collection><collection>OSTI.GOV</collection><jtitle>Journal of the American Ceramic Society</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kamizono, Hiroshi</au><au>Hayakawa, Issei</au><au>Muraoka, Susumu</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Durability of Zirconium-Containing Ceramic Waste Forms in Water</atitle><jtitle>Journal of the American Ceramic Society</jtitle><date>1991-04</date><risdate>1991</risdate><volume>74</volume><issue>4</issue><spage>863</spage><epage>864</epage><pages>863-864</pages><issn>0002-7820</issn><eissn>1551-2916</eissn><coden>JACTAW</coden><abstract>The durability of three ceramic waste forms containing Zr as a constituent is examined at 90° and 150°C in HCl or deionized water. The three ceramic waste forms examined are: (A) 10‐mol%‐Y2O3‐stabilized ZrO2, (B) La2Zr2O7 with a pyrochlore structure, and (C) CaZrO3 with a perovskite structure. Each form contains an appropriate amount of Ce, Nd, and Sr to simulate the leaching behavior of actinides, lanthanides, and alkaline‐earth fission products from highlevel nuclear waste. Two forms, (A) 10‐mol%‐Y2O3‐stabilized ZrO2 and (B) La2Zr2O7 with a pyrochlore structure, show excellent durability in HCl and deionized water. For example, leach rates of all constituents in the La2Zr2O7 waste form are less than about 10−4 g·m−2·d−1 at 150°C for a leach time of 32 d in deionized water.</abstract><cop>Oxford, UK</cop><pub>Blackwell Publishing Ltd</pub><doi>10.1111/j.1151-2916.1991.tb06942.x</doi><tpages>2</tpages></addata></record>
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subjects 052002 - Nuclear Fuels- Waste Disposal & Storage
360205 - Ceramics, Cermets, & Refractories- Corrosion & Erosion
Applied sciences
Building materials. Ceramics. Glasses
Ceramic industries
CERAMICS
CHALCOGENIDES
CHEMICAL COMPOSITION
Chemical industry and chemicals
CHEMICAL PROPERTIES
CHLORINE COMPOUNDS
durability
Exact sciences and technology
geology
HALOGEN COMPOUNDS
HIGH-LEVEL RADIOACTIVE WASTES
HYDROCHLORIC ACID
HYDROGEN COMPOUNDS
INORGANIC ACIDS
Key words
MANAGEMENT
MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
MATERIALS
MATERIALS SCIENCE
MECHANICAL PROPERTIES
Miscellaneous
nuclear waste
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
Technical ceramics
TRANSITION ELEMENT COMPOUNDS
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WASTES
WATER
zirconium
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES
title Durability of Zirconium-Containing Ceramic Waste Forms in Water
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