Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation

Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves p...
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Autor*in:	Digeos, A. A. [verfasserIn] Valdez, J. A. Sickafus, K. E. Atiq, S. Grimes, R. W. Boccaccini, A. R.

Format:	Artikel
Sprache:	Englisch

Erschienen:	2003

Schlagwörter:	Zirconate Heating Rate Encapsulation Solid Waste Lanthanum

Anmerkung:	© Kluwer Academic Publishers 2003

Übergeordnetes Werk:	Enthalten in: Journal of materials science - Kluwer Academic Publishers, 1966, 38(2003), 8 vom: Apr., Seite 1597-1604
Übergeordnetes Werk:	volume:38 ; year:2003 ; number:8 ; month:04 ; pages:1597-1604

Links:	Volltext

DOI / URN:	10.1023/A:1023242702644

Katalog-ID:	OLC204628092X

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520			\|a Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable.
650		4	\|a Zirconate
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allfields	10.1023/A:1023242702644 doi (DE-627)OLC204628092X (DE-He213)A:1023242702644-p DE-627 ger DE-627 rakwb eng 670 VZ Digeos, A. A. verfasserin aut Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation 2003 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic Publishers 2003 Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. Zirconate Heating Rate Encapsulation Solid Waste Lanthanum Valdez, J. A. aut Sickafus, K. E. aut Atiq, S. aut Grimes, R. W. aut Boccaccini, A. R. aut Enthalten in Journal of materials science Kluwer Academic Publishers, 1966 38(2003), 8 vom: Apr., Seite 1597-1604 (DE-627)129546372 (DE-600)218324-9 (DE-576)014996774 0022-2461 nnns volume:38 year:2003 number:8 month:04 pages:1597-1604 https://doi.org/10.1023/A:1023242702644 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC GBV_ILN_20 GBV_ILN_21 GBV_ILN_23 GBV_ILN_30 GBV_ILN_32 GBV_ILN_40 GBV_ILN_62 GBV_ILN_65 GBV_ILN_70 GBV_ILN_100 GBV_ILN_602 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_4046 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4319 GBV_ILN_4323 AR 38 2003 8 04 1597-1604
spelling	10.1023/A:1023242702644 doi (DE-627)OLC204628092X (DE-He213)A:1023242702644-p DE-627 ger DE-627 rakwb eng 670 VZ Digeos, A. A. verfasserin aut Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation 2003 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic Publishers 2003 Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. Zirconate Heating Rate Encapsulation Solid Waste Lanthanum Valdez, J. A. aut Sickafus, K. E. aut Atiq, S. aut Grimes, R. W. aut Boccaccini, A. R. aut Enthalten in Journal of materials science Kluwer Academic Publishers, 1966 38(2003), 8 vom: Apr., Seite 1597-1604 (DE-627)129546372 (DE-600)218324-9 (DE-576)014996774 0022-2461 nnns volume:38 year:2003 number:8 month:04 pages:1597-1604 https://doi.org/10.1023/A:1023242702644 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC GBV_ILN_20 GBV_ILN_21 GBV_ILN_23 GBV_ILN_30 GBV_ILN_32 GBV_ILN_40 GBV_ILN_62 GBV_ILN_65 GBV_ILN_70 GBV_ILN_100 GBV_ILN_602 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_4046 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4319 GBV_ILN_4323 AR 38 2003 8 04 1597-1604
allfields_unstemmed	10.1023/A:1023242702644 doi (DE-627)OLC204628092X (DE-He213)A:1023242702644-p DE-627 ger DE-627 rakwb eng 670 VZ Digeos, A. A. verfasserin aut Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation 2003 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic Publishers 2003 Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. Zirconate Heating Rate Encapsulation Solid Waste Lanthanum Valdez, J. A. aut Sickafus, K. E. aut Atiq, S. aut Grimes, R. W. aut Boccaccini, A. R. aut Enthalten in Journal of materials science Kluwer Academic Publishers, 1966 38(2003), 8 vom: Apr., Seite 1597-1604 (DE-627)129546372 (DE-600)218324-9 (DE-576)014996774 0022-2461 nnns volume:38 year:2003 number:8 month:04 pages:1597-1604 https://doi.org/10.1023/A:1023242702644 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC GBV_ILN_20 GBV_ILN_21 GBV_ILN_23 GBV_ILN_30 GBV_ILN_32 GBV_ILN_40 GBV_ILN_62 GBV_ILN_65 GBV_ILN_70 GBV_ILN_100 GBV_ILN_602 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_4046 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4319 GBV_ILN_4323 AR 38 2003 8 04 1597-1604
allfieldsGer	10.1023/A:1023242702644 doi (DE-627)OLC204628092X (DE-He213)A:1023242702644-p DE-627 ger DE-627 rakwb eng 670 VZ Digeos, A. A. verfasserin aut Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation 2003 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic Publishers 2003 Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. Zirconate Heating Rate Encapsulation Solid Waste Lanthanum Valdez, J. A. aut Sickafus, K. E. aut Atiq, S. aut Grimes, R. W. aut Boccaccini, A. R. aut Enthalten in Journal of materials science Kluwer Academic Publishers, 1966 38(2003), 8 vom: Apr., Seite 1597-1604 (DE-627)129546372 (DE-600)218324-9 (DE-576)014996774 0022-2461 nnns volume:38 year:2003 number:8 month:04 pages:1597-1604 https://doi.org/10.1023/A:1023242702644 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC GBV_ILN_20 GBV_ILN_21 GBV_ILN_23 GBV_ILN_30 GBV_ILN_32 GBV_ILN_40 GBV_ILN_62 GBV_ILN_65 GBV_ILN_70 GBV_ILN_100 GBV_ILN_602 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_4046 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4319 GBV_ILN_4323 AR 38 2003 8 04 1597-1604
allfieldsSound	10.1023/A:1023242702644 doi (DE-627)OLC204628092X (DE-He213)A:1023242702644-p DE-627 ger DE-627 rakwb eng 670 VZ Digeos, A. A. verfasserin aut Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation 2003 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic Publishers 2003 Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. Zirconate Heating Rate Encapsulation Solid Waste Lanthanum Valdez, J. A. aut Sickafus, K. E. aut Atiq, S. aut Grimes, R. W. aut Boccaccini, A. R. aut Enthalten in Journal of materials science Kluwer Academic Publishers, 1966 38(2003), 8 vom: Apr., Seite 1597-1604 (DE-627)129546372 (DE-600)218324-9 (DE-576)014996774 0022-2461 nnns volume:38 year:2003 number:8 month:04 pages:1597-1604 https://doi.org/10.1023/A:1023242702644 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC GBV_ILN_20 GBV_ILN_21 GBV_ILN_23 GBV_ILN_30 GBV_ILN_32 GBV_ILN_40 GBV_ILN_62 GBV_ILN_65 GBV_ILN_70 GBV_ILN_100 GBV_ILN_602 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_4046 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4319 GBV_ILN_4323 AR 38 2003 8 04 1597-1604
language	English
source	Enthalten in Journal of materials science 38(2003), 8 vom: Apr., Seite 1597-1604 volume:38 year:2003 number:8 month:04 pages:1597-1604
sourceStr	Enthalten in Journal of materials science 38(2003), 8 vom: Apr., Seite 1597-1604 volume:38 year:2003 number:8 month:04 pages:1597-1604
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topic_facet	Zirconate Heating Rate Encapsulation Solid Waste Lanthanum
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authorswithroles_txt_mv	Digeos, A. A. @@aut@@ Valdez, J. A. @@aut@@ Sickafus, K. E. @@aut@@ Atiq, S. @@aut@@ Grimes, R. W. @@aut@@ Boccaccini, A. R. @@aut@@
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author	Digeos, A. A.
spellingShingle	Digeos, A. A. ddc 670 misc Zirconate misc Heating Rate misc Encapsulation misc Solid Waste misc Lanthanum Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
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topic_title	670 VZ Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation Zirconate Heating Rate Encapsulation Solid Waste Lanthanum
topic	ddc 670 misc Zirconate misc Heating Rate misc Encapsulation misc Solid Waste misc Lanthanum
topic_unstemmed	ddc 670 misc Zirconate misc Heating Rate misc Encapsulation misc Solid Waste misc Lanthanum
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title	Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
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title_full	Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
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author_browse	Digeos, A. A. Valdez, J. A. Sickafus, K. E. Atiq, S. Grimes, R. W. Boccaccini, A. R.
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title_sort	glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
title_auth	Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
abstract	Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. © Kluwer Academic Publishers 2003
abstractGer	Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. © Kluwer Academic Publishers 2003
abstract_unstemmed	Abstract Novel composite materials have been developed as alternative forms to immobilise nuclear solid waste. These composites are made of a lead-containing glass matrix, into which particles of lanthanum zirconate pyrochlore are embedded in 10 and 30 vol% concentrations. The fabrication involves powder mixing, pressing and pressureless sintering. The processing conditions were investigated with the aim of achieving the highest possible density. The best composites obtained showed a good distribution of the lanthanum zirconate particles in the glass matrix, strong bonding of the particles to the matrix and relatively low porosity (<10%). The best sintering temperature was 600°C for the 10 vol% composite and 650°C for 30 vol%. Sintering was carried out for an hour and a heating rate of 10°C · $ min^{−1} $ was shown to be superior to a heating rate of 2°C · $ min^{−1} $. At the relatively low sintering temperatures used, the pyrochlore crystalline structure of lanthanum zirconate, relevant for containment of radioactive nuclei, was stable. © Kluwer Academic Publishers 2003
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container_issue	8
title_short	Glass matrix/pyrochlore phase composites for nuclear wastes encapsulation
url	https://doi.org/10.1023/A:1023242702644
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author2	Valdez, J. A. Sickafus, K. E. Atiq, S. Grimes, R. W. Boccaccini, A. R.
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