Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials
Irradiation experiments of solid breeder materials including Li 2TiO 3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantli...
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| Veröffentlicht in: | Journal of nuclear materials 2009-04, Vol.386, p.1083-1086 |
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| container_title | Journal of nuclear materials |
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| creator | Hayashi, K. Nakagawa, T. Onose, S. Ishida, T. Nakamichi, M. Takatsu, H. Nakamura, M. Noguchi, T. |
| description | Irradiation experiments of solid breeder materials including Li
2TiO
3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM. |
| doi_str_mv | 10.1016/j.jnucmat.2008.12.290 |
| format | Article |
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2TiO
3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2008.12.290</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Computer simulation ; Controled nuclear fusion plants ; Cutting ; Design engineering ; Dismantling ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Irradiation ; Military technology ; Mockups ; Nuclear fuels ; Nuclear reactor components ; Tritium</subject><ispartof>Journal of nuclear materials, 2009-04, Vol.386, p.1083-1086</ispartof><rights>2009 Elsevier B.V.</rights><rights>2009 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c352t-cbdc9ff44c4e4b93af9187ecb0233aa4452fad1074ad0f5a8fccab513b2b67df3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.jnucmat.2008.12.290$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>310,311,315,781,785,790,791,3551,23935,23936,25145,27929,27930,46000</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=21652397$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Hayashi, K.</creatorcontrib><creatorcontrib>Nakagawa, T.</creatorcontrib><creatorcontrib>Onose, S.</creatorcontrib><creatorcontrib>Ishida, T.</creatorcontrib><creatorcontrib>Nakamichi, M.</creatorcontrib><creatorcontrib>Takatsu, H.</creatorcontrib><creatorcontrib>Nakamura, M.</creatorcontrib><creatorcontrib>Noguchi, T.</creatorcontrib><title>Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials</title><title>Journal of nuclear materials</title><description>Irradiation experiments of solid breeder materials including Li
2TiO
3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM.</description><subject>Applied sciences</subject><subject>Computer simulation</subject><subject>Controled nuclear fusion plants</subject><subject>Cutting</subject><subject>Design engineering</subject><subject>Dismantling</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Irradiation</subject><subject>Military technology</subject><subject>Mockups</subject><subject>Nuclear fuels</subject><subject>Nuclear reactor components</subject><subject>Tritium</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2009</creationdate><recordtype>article</recordtype><recordid>eNqFkUuP1DAQhC0EEsPCT0DyBcElof0aJyeEdnlJK3GBs9XxY-VR4gTbQeLf42FGHOHUl6-qursIecmgZ8COb0_9Ke12wdpzgKFnvOcjPCIHNmjRyYHDY3IA4LwTjKmn5FkpJwBQI6gDKXe-xIdEMTlac8SZBpxytFjjmugaKFIXy4KpzjE9UNw2zFj3QsOaacwZXbygFreyz76cNWWd4x-7GveFTtl75zNtC_pzQnlOnoQ2_IvrvCHfP374dvu5u__66cvt-_vOCsVrZydnxxCktNLLaRQYxnaRtxNwIRClVDygY6AlOggKh2AtToqJiU9H7YK4Ia8vvltef-y-VLPEYv08Y_LrXoweNNdCg2zkm3-STAMDrgY2NFRdUJvXUrIPZstxwfzLMDDnOszJXOsw5zoM46bV0XSvrhFYLM4hY7Kx_BVzdlRcjLpx7y6cb5_5GX02xUafrHcxe1uNW-N_kn4D9mimWA</recordid><startdate>20090430</startdate><enddate>20090430</enddate><creator>Hayashi, K.</creator><creator>Nakagawa, T.</creator><creator>Onose, S.</creator><creator>Ishida, T.</creator><creator>Nakamichi, M.</creator><creator>Takatsu, H.</creator><creator>Nakamura, M.</creator><creator>Noguchi, T.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>7TV</scope><scope>C1K</scope></search><sort><creationdate>20090430</creationdate><title>Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials</title><author>Hayashi, K. ; Nakagawa, T. ; Onose, S. ; Ishida, T. ; Nakamichi, M. ; Takatsu, H. ; Nakamura, M. ; Noguchi, T.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c352t-cbdc9ff44c4e4b93af9187ecb0233aa4452fad1074ad0f5a8fccab513b2b67df3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2009</creationdate><topic>Applied sciences</topic><topic>Computer simulation</topic><topic>Controled nuclear fusion plants</topic><topic>Cutting</topic><topic>Design engineering</topic><topic>Dismantling</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Irradiation</topic><topic>Military technology</topic><topic>Mockups</topic><topic>Nuclear fuels</topic><topic>Nuclear reactor components</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Hayashi, K.</creatorcontrib><creatorcontrib>Nakagawa, T.</creatorcontrib><creatorcontrib>Onose, S.</creatorcontrib><creatorcontrib>Ishida, T.</creatorcontrib><creatorcontrib>Nakamichi, M.</creatorcontrib><creatorcontrib>Takatsu, H.</creatorcontrib><creatorcontrib>Nakamura, M.</creatorcontrib><creatorcontrib>Noguchi, T.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Pollution Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Hayashi, K.</au><au>Nakagawa, T.</au><au>Onose, S.</au><au>Ishida, T.</au><au>Nakamichi, M.</au><au>Takatsu, H.</au><au>Nakamura, M.</au><au>Noguchi, T.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials</atitle><jtitle>Journal of nuclear materials</jtitle><date>2009-04-30</date><risdate>2009</risdate><volume>386</volume><spage>1083</spage><epage>1086</epage><pages>1083-1086</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>Irradiation experiments of solid breeder materials including Li
2TiO
3 have been being carried out in preparation for a test blanket module (TBM) of the International Thermonuclear Experimental Reactor (ITER). The present paper deals with design and trial-fabrication works for developing a dismantling apparatus for the irradiation capsules. The dismantling process leads to release of tritium which is left in free volumes of the capsule or in the breeder specimens. In the design of the dismantling apparatus, the released tritium is recovered safely by a purge-gas system during the cutting of the irradiation capsule by a band saw, and then the tritium is consolidated into a radioactive waste. Furthermore, an inner-box enclosing the dismantling apparatus works as a countermeasure of possible release of tritium in accidental events. Good performance of a trial fabrication model of the dismantling apparatus has been demonstrated by preliminary cutting runs using some mockups simulating the irradiation capsules. Thus, the present design of the apparatus, together with the trial mock-up runs, will contribute to the design of the TBM structure and to the planning of the dismantling process of the TBM.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2008.12.290</doi><tpages>4</tpages></addata></record> |
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| ispartof | Journal of nuclear materials, 2009-04, Vol.386, p.1083-1086 |
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| language | eng |
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| subjects | Applied sciences Computer simulation Controled nuclear fusion plants Cutting Design engineering Dismantling Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Irradiation Military technology Mockups Nuclear fuels Nuclear reactor components Tritium |
| title | Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials |
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