Influence of rock properties on selection of design for a spent nuclear fuel repository
In Sweden, researchers are examining designs for a repository for storage of spent nuclear fuel. By the year 2010 (when nuclear power production will cease, according to parliamentary decision), approximately 10,000 m 3 of spent fuel will need to be encapsulated in the repository. One such system, t...
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Veröffentlicht in: | Tunnelling and underground space technology 1993, Vol.8 (3), p.345-356 |
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description | In Sweden, researchers are examining designs for a repository for storage of spent nuclear fuel. By the year 2010 (when nuclear power production will cease, according to parliamentary decision), approximately 10,000 m
3 of spent fuel will need to be encapsulated in the repository. One such system, the KBS-3 (abbreviation for Nuclear Fuel Safety, in English), has been evaluated over the past decade. Another design, called the Very Long Hole (VLH) system, is also being considered. The main difference between the two systems is in the shape of the rock openings in the disposal areas. This paper analyzes the properties of the rock in the near field (i.e., the rock affected by the excavation of the repository) and compares them for the two repository systems.
En Suède, les chercheurs étudient les propositions de conception d'un dépôt pour le stockage du combustible nucléaire irradié. D'ici l'année 2010 (quand la production d'énergie nucléaire cessera, selon une décision parlementaire), environ 10,000 m3 de combustible irradié devra être mis en capsules dans le dépôt. Un tel système, le KBS-3 (abreeviation pour Sécurité du combusible nucléaire), a été évalué lors de la dernière décennie. Une autre conception, appelée le Système Very Long Hole (VLH) (Trés long trou) est aussi pris en considération. La principale différence entre les deux systèmes réside dans la forme des ouvertures dans la roche sur les sites de dépôt. Ce document analyse les proprieetés de la roche dans le champ avoisinant (la roche endommagée pour l'excavation du dép^ot) et les compare dans les deux systèmes de dépôt. |
doi_str_mv | 10.1016/0886-7798(93)90019-R |
format | Article |
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En Suède, les chercheurs étudient les propositions de conception d'un dépôt pour le stockage du combustible nucléaire irradié. D'ici l'année 2010 (quand la production d'énergie nucléaire cessera, selon une décision parlementaire), environ 10,000 m3 de combustible irradié devra être mis en capsules dans le dépôt. Un tel système, le KBS-3 (abreeviation pour Sécurité du combusible nucléaire), a été évalué lors de la dernière décennie. Une autre conception, appelée le Système Very Long Hole (VLH) (Trés long trou) est aussi pris en considération. La principale différence entre les deux systèmes réside dans la forme des ouvertures dans la roche sur les sites de dépôt. Ce document analyse les proprieetés de la roche dans le champ avoisinant (la roche endommagée pour l'excavation du dép^ot) et les compare dans les deux systèmes de dépôt.</description><identifier>ISSN: 0886-7798</identifier><identifier>EISSN: 1878-4364</identifier><identifier>DOI: 10.1016/0886-7798(93)90019-R</identifier><identifier>CODEN: TUSTEQ</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Earth sciences ; Earth, ocean, space ; Engineering and environment geology. Geothermics ; Engineering geology ; Exact sciences and technology</subject><ispartof>Tunnelling and underground space technology, 1993, Vol.8 (3), p.345-356</ispartof><rights>1993</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-a387t-cc92d7bc1efe4da64786c7358416bd84c69425d7aa265830c6bc362b8ce501f83</citedby><cites>FETCH-LOGICAL-a387t-cc92d7bc1efe4da64786c7358416bd84c69425d7aa265830c6bc362b8ce501f83</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/0886-7798(93)90019-R$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,4024,27923,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=6475637$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Pusch, Roland</creatorcontrib><creatorcontrib>Svemar, Christer</creatorcontrib><title>Influence of rock properties on selection of design for a spent nuclear fuel repository</title><title>Tunnelling and underground space technology</title><description>In Sweden, researchers are examining designs for a repository for storage of spent nuclear fuel. By the year 2010 (when nuclear power production will cease, according to parliamentary decision), approximately 10,000 m
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En Suède, les chercheurs étudient les propositions de conception d'un dépôt pour le stockage du combustible nucléaire irradié. D'ici l'année 2010 (quand la production d'énergie nucléaire cessera, selon une décision parlementaire), environ 10,000 m3 de combustible irradié devra être mis en capsules dans le dépôt. Un tel système, le KBS-3 (abreeviation pour Sécurité du combusible nucléaire), a été évalué lors de la dernière décennie. Une autre conception, appelée le Système Very Long Hole (VLH) (Trés long trou) est aussi pris en considération. La principale différence entre les deux systèmes réside dans la forme des ouvertures dans la roche sur les sites de dépôt. Ce document analyse les proprieetés de la roche dans le champ avoisinant (la roche endommagée pour l'excavation du dép^ot) et les compare dans les deux systèmes de dépôt.</description><subject>Earth sciences</subject><subject>Earth, ocean, space</subject><subject>Engineering and environment geology. Geothermics</subject><subject>Engineering geology</subject><subject>Exact sciences and technology</subject><issn>0886-7798</issn><issn>1878-4364</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1993</creationdate><recordtype>article</recordtype><recordid>eNp9kEtrGzEQgEVpIa7Tf5CDDiE0h22k1a4el0AxSWMwFExDjkKeHRW169VG2g3431euQ445zcB88_oIueDsG2dc3jCtZaWU0V-NuDaMcVNtP5AF10pXjZDNR7J4Q87I55z_MMbaujYL8rQefD_jAEijpynCXzqmOGKaAmYaB5qxR5hCyUq9wxx-D9THRB3NIw4THWbo0SXqZ-xpwjHmMMV0OCefvOszfnmNS_J4f_dr9VBtfv5Yr75vKie0mioAU3dqBxw9Np2TjdISlGh1w-Wu0w1I09Rtp5yrZasFA7kDIeudBmwZ91osydVpbrn6ecY82X3IgH3vBoxztly2Rta1KGBzAiHFnBN6O6awd-lgObNHi_aoyB4VWSPsf4t2W9ouX-e7DK73yQ0Q8ltvObiVQhXs9oRh-fUlYLIZwtFqF1LRZ7sY3t_zD45Dhx4</recordid><startdate>1993</startdate><enddate>1993</enddate><creator>Pusch, Roland</creator><creator>Svemar, Christer</creator><general>Elsevier Ltd</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7T2</scope><scope>7TV</scope><scope>7U2</scope><scope>C1K</scope></search><sort><creationdate>1993</creationdate><title>Influence of rock properties on selection of design for a spent nuclear fuel repository</title><author>Pusch, Roland ; Svemar, Christer</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-a387t-cc92d7bc1efe4da64786c7358416bd84c69425d7aa265830c6bc362b8ce501f83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1993</creationdate><topic>Earth sciences</topic><topic>Earth, ocean, space</topic><topic>Engineering and environment geology. Geothermics</topic><topic>Engineering geology</topic><topic>Exact sciences and technology</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Pusch, Roland</creatorcontrib><creatorcontrib>Svemar, Christer</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Health and Safety Science Abstracts (Full archive)</collection><collection>Pollution Abstracts</collection><collection>Safety Science and Risk</collection><collection>Environmental Sciences and Pollution Management</collection><jtitle>Tunnelling and underground space technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Pusch, Roland</au><au>Svemar, Christer</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Influence of rock properties on selection of design for a spent nuclear fuel repository</atitle><jtitle>Tunnelling and underground space technology</jtitle><date>1993</date><risdate>1993</risdate><volume>8</volume><issue>3</issue><spage>345</spage><epage>356</epage><pages>345-356</pages><issn>0886-7798</issn><eissn>1878-4364</eissn><coden>TUSTEQ</coden><abstract>In Sweden, researchers are examining designs for a repository for storage of spent nuclear fuel. By the year 2010 (when nuclear power production will cease, according to parliamentary decision), approximately 10,000 m
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En Suède, les chercheurs étudient les propositions de conception d'un dépôt pour le stockage du combustible nucléaire irradié. D'ici l'année 2010 (quand la production d'énergie nucléaire cessera, selon une décision parlementaire), environ 10,000 m3 de combustible irradié devra être mis en capsules dans le dépôt. Un tel système, le KBS-3 (abreeviation pour Sécurité du combusible nucléaire), a été évalué lors de la dernière décennie. Une autre conception, appelée le Système Very Long Hole (VLH) (Trés long trou) est aussi pris en considération. La principale différence entre les deux systèmes réside dans la forme des ouvertures dans la roche sur les sites de dépôt. Ce document analyse les proprieetés de la roche dans le champ avoisinant (la roche endommagée pour l'excavation du dép^ot) et les compare dans les deux systèmes de dépôt.</abstract><cop>Oxford</cop><pub>Elsevier Ltd</pub><doi>10.1016/0886-7798(93)90019-R</doi><tpages>12</tpages></addata></record> |
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subjects | Earth sciences Earth, ocean, space Engineering and environment geology. Geothermics Engineering geology Exact sciences and technology |
title | Influence of rock properties on selection of design for a spent nuclear fuel repository |
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