A disposal-MOX concept for plutonium disposition
In case it is desirable to dispose of inventories of separated civil PuO 2 that have no further use, a suitable immobilisation matrix is required, prior to disposition in a geological disposal facility. Conversion of Pu into a mixed oxide (MOX)-type material with characteristics suitable for disposa...
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creator | Cole, Max R Blackburn, Lewis R Haigh, Latham T Bailey, Daniel J Townsend, Luke T Kvashnina, Kristina O Hyatt, Neil C Corkhill, Claire L |
description | In case it is desirable to dispose of inventories of separated civil PuO
2
that have no further use, a suitable immobilisation matrix is required, prior to disposition in a geological disposal facility. Conversion of Pu into a mixed oxide (MOX)-type material with characteristics suitable for disposal has previously been suggested, but not yet demonstrated at laboratory or industrial scale. We here demonstrate the feasibility of different synthesis routes for simulant "disposal-MOX", using Th
4+
as a Pu
4+
surrogate and containing Gd
3+
in a suitable quantity to ensure criticality control. Compositions of (U
(1−(
x
+
y
))
Th
x
Gd
y
)O
2−
δ
, where
x
= 0.1, 0.2 and
x
:
y
= 10 : 1 or 100 : 1, were synthesised by a solid state route mimicking the industrial MIMAS (MIcronized MASterblend) MOX fuel fabrication process, or through an oxalic wet co-precipitation method. Both synthesis routes gave a single phase fluorite structure upon heat-treatment at 1700 °C, with a grain size similar to (Pu,U)O
2
MOX fuel. The relative density of the sintered pellets was >90% but was highest in co-precipitated materials, with Th
4+
and Gd
3+
additions more homogenously distributed. Though no unincorporated ThO
2
or Gd
2
O
3
was observed in any sample, Th and Gd-rich regions were more prevalent in materials produced through solid state synthesis, in accordance with MIMAS MOX fuel microstructures. The incorporation of Gd
3+
within the fluorite lattice, which is favourable from a criticality control perspective in a Pu wasteform, was found to be charge balanced
via
the generation of oxygen vacancy defects, but not U
5+
. These results demonstrate feasible synthesis routes for a disposal-MOX wasteform product
via
both solid state and wet co-precipitation fabrication routes.
The feasibility of disposal-MOX as a ceramic wasteform for inventories of separated civil PuO
2
is demonstrated
via
two fabrication routes. Both use Th
4+
as a surrogate for Pu
4+
, and Gd
3+
is incorporated for criticality control. |
doi_str_mv | 10.1039/d4ma00420e |
format | Article |
fullrecord | <record><control><sourceid>rsc_cross</sourceid><recordid>TN_cdi_crossref_primary_10_1039_D4MA00420E</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>d4ma00420e</sourcerecordid><originalsourceid>FETCH-LOGICAL-c178t-f096f6c33f0a8cda2ea7a06fbc0f0412e11df7297e6e1337873b50068aac160c3</originalsourceid><addsrcrecordid>eNpNkM9LwzAYhoMoOOYu3oWehej3JWnSHMucU9jYRcFbydIEIm1Tku7gf--PDfX0voeHF56XkGuEOwSu71vRGwDBwJ2RGZOc01KAPv_XL8ki53cAYCWi1nJGoC7akMeYTUe3u7fCxsG6cSp8TMXYHaY4hEN_QsIU4nBFLrzpslucck5eH1cvyye62a2fl_WGWlTVRD1o6aXl3IOpbGuYM8qA9HsLHgQyh9h6xbRy0iHnqlJ8XwLIyhiLEiyfk9vjrk0x5-R8M6bQm_TRIDTfus2D2NY_uqsv-OYIp2x_ub87-CcCeVDE</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>A disposal-MOX concept for plutonium disposition</title><source>DOAJ Directory of Open Access Journals</source><source>EZB-FREE-00999 freely available EZB journals</source><creator>Cole, Max R ; Blackburn, Lewis R ; Haigh, Latham T ; Bailey, Daniel J ; Townsend, Luke T ; Kvashnina, Kristina O ; Hyatt, Neil C ; Corkhill, Claire L</creator><creatorcontrib>Cole, Max R ; Blackburn, Lewis R ; Haigh, Latham T ; Bailey, Daniel J ; Townsend, Luke T ; Kvashnina, Kristina O ; Hyatt, Neil C ; Corkhill, Claire L</creatorcontrib><description>In case it is desirable to dispose of inventories of separated civil PuO
2
that have no further use, a suitable immobilisation matrix is required, prior to disposition in a geological disposal facility. Conversion of Pu into a mixed oxide (MOX)-type material with characteristics suitable for disposal has previously been suggested, but not yet demonstrated at laboratory or industrial scale. We here demonstrate the feasibility of different synthesis routes for simulant "disposal-MOX", using Th
4+
as a Pu
4+
surrogate and containing Gd
3+
in a suitable quantity to ensure criticality control. Compositions of (U
(1−(
x
+
y
))
Th
x
Gd
y
)O
2−
δ
, where
x
= 0.1, 0.2 and
x
:
y
= 10 : 1 or 100 : 1, were synthesised by a solid state route mimicking the industrial MIMAS (MIcronized MASterblend) MOX fuel fabrication process, or through an oxalic wet co-precipitation method. Both synthesis routes gave a single phase fluorite structure upon heat-treatment at 1700 °C, with a grain size similar to (Pu,U)O
2
MOX fuel. The relative density of the sintered pellets was >90% but was highest in co-precipitated materials, with Th
4+
and Gd
3+
additions more homogenously distributed. Though no unincorporated ThO
2
or Gd
2
O
3
was observed in any sample, Th and Gd-rich regions were more prevalent in materials produced through solid state synthesis, in accordance with MIMAS MOX fuel microstructures. The incorporation of Gd
3+
within the fluorite lattice, which is favourable from a criticality control perspective in a Pu wasteform, was found to be charge balanced
via
the generation of oxygen vacancy defects, but not U
5+
. These results demonstrate feasible synthesis routes for a disposal-MOX wasteform product
via
both solid state and wet co-precipitation fabrication routes.
The feasibility of disposal-MOX as a ceramic wasteform for inventories of separated civil PuO
2
is demonstrated
via
two fabrication routes. Both use Th
4+
as a surrogate for Pu
4+
, and Gd
3+
is incorporated for criticality control.</description><identifier>ISSN: 2633-5409</identifier><identifier>EISSN: 2633-5409</identifier><identifier>DOI: 10.1039/d4ma00420e</identifier><language>eng</language><ispartof>Materials advances, 2024-08, Vol.5 (16), p.6416-6425</ispartof><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c178t-f096f6c33f0a8cda2ea7a06fbc0f0412e11df7297e6e1337873b50068aac160c3</cites><orcidid>0000-0002-7488-3219 ; 0000-0001-8752-8374</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,864,27924,27925</link.rule.ids></links><search><creatorcontrib>Cole, Max R</creatorcontrib><creatorcontrib>Blackburn, Lewis R</creatorcontrib><creatorcontrib>Haigh, Latham T</creatorcontrib><creatorcontrib>Bailey, Daniel J</creatorcontrib><creatorcontrib>Townsend, Luke T</creatorcontrib><creatorcontrib>Kvashnina, Kristina O</creatorcontrib><creatorcontrib>Hyatt, Neil C</creatorcontrib><creatorcontrib>Corkhill, Claire L</creatorcontrib><title>A disposal-MOX concept for plutonium disposition</title><title>Materials advances</title><description>In case it is desirable to dispose of inventories of separated civil PuO
2
that have no further use, a suitable immobilisation matrix is required, prior to disposition in a geological disposal facility. Conversion of Pu into a mixed oxide (MOX)-type material with characteristics suitable for disposal has previously been suggested, but not yet demonstrated at laboratory or industrial scale. We here demonstrate the feasibility of different synthesis routes for simulant "disposal-MOX", using Th
4+
as a Pu
4+
surrogate and containing Gd
3+
in a suitable quantity to ensure criticality control. Compositions of (U
(1−(
x
+
y
))
Th
x
Gd
y
)O
2−
δ
, where
x
= 0.1, 0.2 and
x
:
y
= 10 : 1 or 100 : 1, were synthesised by a solid state route mimicking the industrial MIMAS (MIcronized MASterblend) MOX fuel fabrication process, or through an oxalic wet co-precipitation method. Both synthesis routes gave a single phase fluorite structure upon heat-treatment at 1700 °C, with a grain size similar to (Pu,U)O
2
MOX fuel. The relative density of the sintered pellets was >90% but was highest in co-precipitated materials, with Th
4+
and Gd
3+
additions more homogenously distributed. Though no unincorporated ThO
2
or Gd
2
O
3
was observed in any sample, Th and Gd-rich regions were more prevalent in materials produced through solid state synthesis, in accordance with MIMAS MOX fuel microstructures. The incorporation of Gd
3+
within the fluorite lattice, which is favourable from a criticality control perspective in a Pu wasteform, was found to be charge balanced
via
the generation of oxygen vacancy defects, but not U
5+
. These results demonstrate feasible synthesis routes for a disposal-MOX wasteform product
via
both solid state and wet co-precipitation fabrication routes.
The feasibility of disposal-MOX as a ceramic wasteform for inventories of separated civil PuO
2
is demonstrated
via
two fabrication routes. Both use Th
4+
as a surrogate for Pu
4+
, and Gd
3+
is incorporated for criticality control.</description><issn>2633-5409</issn><issn>2633-5409</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><recordid>eNpNkM9LwzAYhoMoOOYu3oWehej3JWnSHMucU9jYRcFbydIEIm1Tku7gf--PDfX0voeHF56XkGuEOwSu71vRGwDBwJ2RGZOc01KAPv_XL8ki53cAYCWi1nJGoC7akMeYTUe3u7fCxsG6cSp8TMXYHaY4hEN_QsIU4nBFLrzpslucck5eH1cvyye62a2fl_WGWlTVRD1o6aXl3IOpbGuYM8qA9HsLHgQyh9h6xbRy0iHnqlJ8XwLIyhiLEiyfk9vjrk0x5-R8M6bQm_TRIDTfus2D2NY_uqsv-OYIp2x_ub87-CcCeVDE</recordid><startdate>20240812</startdate><enddate>20240812</enddate><creator>Cole, Max R</creator><creator>Blackburn, Lewis R</creator><creator>Haigh, Latham T</creator><creator>Bailey, Daniel J</creator><creator>Townsend, Luke T</creator><creator>Kvashnina, Kristina O</creator><creator>Hyatt, Neil C</creator><creator>Corkhill, Claire L</creator><scope>AAYXX</scope><scope>CITATION</scope><orcidid>https://orcid.org/0000-0002-7488-3219</orcidid><orcidid>https://orcid.org/0000-0001-8752-8374</orcidid></search><sort><creationdate>20240812</creationdate><title>A disposal-MOX concept for plutonium disposition</title><author>Cole, Max R ; Blackburn, Lewis R ; Haigh, Latham T ; Bailey, Daniel J ; Townsend, Luke T ; Kvashnina, Kristina O ; Hyatt, Neil C ; Corkhill, Claire L</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c178t-f096f6c33f0a8cda2ea7a06fbc0f0412e11df7297e6e1337873b50068aac160c3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Cole, Max R</creatorcontrib><creatorcontrib>Blackburn, Lewis R</creatorcontrib><creatorcontrib>Haigh, Latham T</creatorcontrib><creatorcontrib>Bailey, Daniel J</creatorcontrib><creatorcontrib>Townsend, Luke T</creatorcontrib><creatorcontrib>Kvashnina, Kristina O</creatorcontrib><creatorcontrib>Hyatt, Neil C</creatorcontrib><creatorcontrib>Corkhill, Claire L</creatorcontrib><collection>CrossRef</collection><jtitle>Materials advances</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Cole, Max R</au><au>Blackburn, Lewis R</au><au>Haigh, Latham T</au><au>Bailey, Daniel J</au><au>Townsend, Luke T</au><au>Kvashnina, Kristina O</au><au>Hyatt, Neil C</au><au>Corkhill, Claire L</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>A disposal-MOX concept for plutonium disposition</atitle><jtitle>Materials advances</jtitle><date>2024-08-12</date><risdate>2024</risdate><volume>5</volume><issue>16</issue><spage>6416</spage><epage>6425</epage><pages>6416-6425</pages><issn>2633-5409</issn><eissn>2633-5409</eissn><abstract>In case it is desirable to dispose of inventories of separated civil PuO
2
that have no further use, a suitable immobilisation matrix is required, prior to disposition in a geological disposal facility. Conversion of Pu into a mixed oxide (MOX)-type material with characteristics suitable for disposal has previously been suggested, but not yet demonstrated at laboratory or industrial scale. We here demonstrate the feasibility of different synthesis routes for simulant "disposal-MOX", using Th
4+
as a Pu
4+
surrogate and containing Gd
3+
in a suitable quantity to ensure criticality control. Compositions of (U
(1−(
x
+
y
))
Th
x
Gd
y
)O
2−
δ
, where
x
= 0.1, 0.2 and
x
:
y
= 10 : 1 or 100 : 1, were synthesised by a solid state route mimicking the industrial MIMAS (MIcronized MASterblend) MOX fuel fabrication process, or through an oxalic wet co-precipitation method. Both synthesis routes gave a single phase fluorite structure upon heat-treatment at 1700 °C, with a grain size similar to (Pu,U)O
2
MOX fuel. The relative density of the sintered pellets was >90% but was highest in co-precipitated materials, with Th
4+
and Gd
3+
additions more homogenously distributed. Though no unincorporated ThO
2
or Gd
2
O
3
was observed in any sample, Th and Gd-rich regions were more prevalent in materials produced through solid state synthesis, in accordance with MIMAS MOX fuel microstructures. The incorporation of Gd
3+
within the fluorite lattice, which is favourable from a criticality control perspective in a Pu wasteform, was found to be charge balanced
via
the generation of oxygen vacancy defects, but not U
5+
. These results demonstrate feasible synthesis routes for a disposal-MOX wasteform product
via
both solid state and wet co-precipitation fabrication routes.
The feasibility of disposal-MOX as a ceramic wasteform for inventories of separated civil PuO
2
is demonstrated
via
two fabrication routes. Both use Th
4+
as a surrogate for Pu
4+
, and Gd
3+
is incorporated for criticality control.</abstract><doi>10.1039/d4ma00420e</doi><tpages>1</tpages><orcidid>https://orcid.org/0000-0002-7488-3219</orcidid><orcidid>https://orcid.org/0000-0001-8752-8374</orcidid><oa>free_for_read</oa></addata></record> |
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title | A disposal-MOX concept for plutonium disposition |
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