Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment
The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a cohe...
Gespeichert in:
Veröffentlicht in: | arXiv.org 2014-08 |
---|---|
Hauptverfasser: | , , , , , , , , , , , , , , , , , , , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
container_end_page | |
---|---|
container_issue | |
container_start_page | |
container_title | arXiv.org |
container_volume | |
creator | Stork, D Agostini, P J-L Boutard Buckthorpe, D Diegele, E Dudarev, S L English, C Federici, G Gilbert, M R Gonzalez, S Ibarra, A Linsmeier, Ch A Li Puma Marbach, G Morris, P F Packer, L W Raj, B Rieth, M Tran, M Q Ward, D J Zinkle, S J |
description | The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a coherent strategy for R&D up to a DEMO construction decision. Technical consequences for the materials required and the development, testing and modelling programmes, are analysed using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants; and a project-based risk analysis, with R&D to mitigate risks from material shortcomings including development of specific risk mitigation materials. |
doi_str_mv | 10.48550/arxiv.1408.3546 |
format | Article |
fullrecord | <record><control><sourceid>proquest_arxiv</sourceid><recordid>TN_cdi_arxiv_primary_1408_3546</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>2084591459</sourcerecordid><originalsourceid>FETCH-LOGICAL-a519-c9561321e130d9205e7f73a3949721f939128c4fd9c97196a7ecbde13aa79b093</originalsourceid><addsrcrecordid>eNotkE1rwkAQhpdCoWK991QGem3sfmSTbG_iRy0oCrXnMCYbjeTD7m7UQn98k9rDMDA878vwEPLA6NCPpKQvaC75ach8Gg2F9IMb0uNCMC_yOb8jA2sPlFIehFxK0SM_E33SRX3Mqx18ONMkrjFYPMM83-29vUYHWdFcAKsU1gXaEmGGSQcv0WmTY2Ehqw0gVBqN155KmEyXK5g1Nq8rWNdnbbpk5V7B7TVMP2Fkrba21JW7J7dZ26AH_7tPNrPpZjz3Fqu39_Fo4aFkykuUDJjgTDNBU8Wp1GEWChTKVyFnmRKK8Sjxs1QlKmQqwFAn27SlEUO1pUr0yeO19s9MfDR5ieY77gzFnaEWeLoCR1N_Ndq6-FA3pmpfijmNfKlYO-IXkkZoDQ</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2084591459</pqid></control><display><type>article</type><title>Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment</title><source>arXiv.org</source><source>Free E- Journals</source><creator>Stork, D ; Agostini, P ; J-L Boutard ; Buckthorpe, D ; Diegele, E ; Dudarev, S L ; English, C ; Federici, G ; Gilbert, M R ; Gonzalez, S ; Ibarra, A ; Linsmeier, Ch ; A Li Puma ; Marbach, G ; Morris, P F ; Packer, L W ; Raj, B ; Rieth, M ; Tran, M Q ; Ward, D J ; Zinkle, S J</creator><creatorcontrib>Stork, D ; Agostini, P ; J-L Boutard ; Buckthorpe, D ; Diegele, E ; Dudarev, S L ; English, C ; Federici, G ; Gilbert, M R ; Gonzalez, S ; Ibarra, A ; Linsmeier, Ch ; A Li Puma ; Marbach, G ; Morris, P F ; Packer, L W ; Raj, B ; Rieth, M ; Tran, M Q ; Ward, D J ; Zinkle, S J</creatorcontrib><description>The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a coherent strategy for R&D up to a DEMO construction decision. Technical consequences for the materials required and the development, testing and modelling programmes, are analysed using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants; and a project-based risk analysis, with R&D to mitigate risks from material shortcomings including development of specific risk mitigation materials.</description><identifier>EISSN: 2331-8422</identifier><identifier>DOI: 10.48550/arxiv.1408.3546</identifier><language>eng</language><publisher>Ithaca: Cornell University Library, arXiv.org</publisher><subject>Coolants ; Electric power generation ; Functional materials ; Heat flux ; Heat transfer ; Inspection ; Nuclear power plants ; Physics - Instrumentation and Detectors ; R&D ; Research & development ; Risk analysis ; Systems engineering</subject><ispartof>arXiv.org, 2014-08</ispartof><rights>2014. This work is published under http://arxiv.org/licenses/nonexclusive-distrib/1.0/ (the “License”). Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License.</rights><rights>http://arxiv.org/licenses/nonexclusive-distrib/1.0</rights><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>228,230,776,780,881,27904</link.rule.ids><backlink>$$Uhttps://doi.org/10.48550/arXiv.1408.3546$$DView paper in arXiv$$Hfree_for_read</backlink><backlink>$$Uhttps://doi.org/10.1016/j.jnucmat.2014.06.014$$DView published paper (Access to full text may be restricted)$$Hfree_for_read</backlink></links><search><creatorcontrib>Stork, D</creatorcontrib><creatorcontrib>Agostini, P</creatorcontrib><creatorcontrib>J-L Boutard</creatorcontrib><creatorcontrib>Buckthorpe, D</creatorcontrib><creatorcontrib>Diegele, E</creatorcontrib><creatorcontrib>Dudarev, S L</creatorcontrib><creatorcontrib>English, C</creatorcontrib><creatorcontrib>Federici, G</creatorcontrib><creatorcontrib>Gilbert, M R</creatorcontrib><creatorcontrib>Gonzalez, S</creatorcontrib><creatorcontrib>Ibarra, A</creatorcontrib><creatorcontrib>Linsmeier, Ch</creatorcontrib><creatorcontrib>A Li Puma</creatorcontrib><creatorcontrib>Marbach, G</creatorcontrib><creatorcontrib>Morris, P F</creatorcontrib><creatorcontrib>Packer, L W</creatorcontrib><creatorcontrib>Raj, B</creatorcontrib><creatorcontrib>Rieth, M</creatorcontrib><creatorcontrib>Tran, M Q</creatorcontrib><creatorcontrib>Ward, D J</creatorcontrib><creatorcontrib>Zinkle, S J</creatorcontrib><title>Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment</title><title>arXiv.org</title><description>The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a coherent strategy for R&D up to a DEMO construction decision. Technical consequences for the materials required and the development, testing and modelling programmes, are analysed using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants; and a project-based risk analysis, with R&D to mitigate risks from material shortcomings including development of specific risk mitigation materials.</description><subject>Coolants</subject><subject>Electric power generation</subject><subject>Functional materials</subject><subject>Heat flux</subject><subject>Heat transfer</subject><subject>Inspection</subject><subject>Nuclear power plants</subject><subject>Physics - Instrumentation and Detectors</subject><subject>R&D</subject><subject>Research & development</subject><subject>Risk analysis</subject><subject>Systems engineering</subject><issn>2331-8422</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GOX</sourceid><recordid>eNotkE1rwkAQhpdCoWK991QGem3sfmSTbG_iRy0oCrXnMCYbjeTD7m7UQn98k9rDMDA878vwEPLA6NCPpKQvaC75ach8Gg2F9IMb0uNCMC_yOb8jA2sPlFIehFxK0SM_E33SRX3Mqx18ONMkrjFYPMM83-29vUYHWdFcAKsU1gXaEmGGSQcv0WmTY2Ehqw0gVBqN155KmEyXK5g1Nq8rWNdnbbpk5V7B7TVMP2Fkrba21JW7J7dZ26AH_7tPNrPpZjz3Fqu39_Fo4aFkykuUDJjgTDNBU8Wp1GEWChTKVyFnmRKK8Sjxs1QlKmQqwFAn27SlEUO1pUr0yeO19s9MfDR5ieY77gzFnaEWeLoCR1N_Ndq6-FA3pmpfijmNfKlYO-IXkkZoDQ</recordid><startdate>20140814</startdate><enddate>20140814</enddate><creator>Stork, D</creator><creator>Agostini, P</creator><creator>J-L Boutard</creator><creator>Buckthorpe, D</creator><creator>Diegele, E</creator><creator>Dudarev, S L</creator><creator>English, C</creator><creator>Federici, G</creator><creator>Gilbert, M R</creator><creator>Gonzalez, S</creator><creator>Ibarra, A</creator><creator>Linsmeier, Ch</creator><creator>A Li Puma</creator><creator>Marbach, G</creator><creator>Morris, P F</creator><creator>Packer, L W</creator><creator>Raj, B</creator><creator>Rieth, M</creator><creator>Tran, M Q</creator><creator>Ward, D J</creator><creator>Zinkle, S J</creator><general>Cornell University Library, arXiv.org</general><scope>8FE</scope><scope>8FG</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>HCIFZ</scope><scope>L6V</scope><scope>M7S</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PRINS</scope><scope>PTHSS</scope><scope>GOX</scope></search><sort><creationdate>20140814</creationdate><title>Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment</title><author>Stork, D ; Agostini, P ; J-L Boutard ; Buckthorpe, D ; Diegele, E ; Dudarev, S L ; English, C ; Federici, G ; Gilbert, M R ; Gonzalez, S ; Ibarra, A ; Linsmeier, Ch ; A Li Puma ; Marbach, G ; Morris, P F ; Packer, L W ; Raj, B ; Rieth, M ; Tran, M Q ; Ward, D J ; Zinkle, S J</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-a519-c9561321e130d9205e7f73a3949721f939128c4fd9c97196a7ecbde13aa79b093</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Coolants</topic><topic>Electric power generation</topic><topic>Functional materials</topic><topic>Heat flux</topic><topic>Heat transfer</topic><topic>Inspection</topic><topic>Nuclear power plants</topic><topic>Physics - Instrumentation and Detectors</topic><topic>R&D</topic><topic>Research & development</topic><topic>Risk analysis</topic><topic>Systems engineering</topic><toplevel>online_resources</toplevel><creatorcontrib>Stork, D</creatorcontrib><creatorcontrib>Agostini, P</creatorcontrib><creatorcontrib>J-L Boutard</creatorcontrib><creatorcontrib>Buckthorpe, D</creatorcontrib><creatorcontrib>Diegele, E</creatorcontrib><creatorcontrib>Dudarev, S L</creatorcontrib><creatorcontrib>English, C</creatorcontrib><creatorcontrib>Federici, G</creatorcontrib><creatorcontrib>Gilbert, M R</creatorcontrib><creatorcontrib>Gonzalez, S</creatorcontrib><creatorcontrib>Ibarra, A</creatorcontrib><creatorcontrib>Linsmeier, Ch</creatorcontrib><creatorcontrib>A Li Puma</creatorcontrib><creatorcontrib>Marbach, G</creatorcontrib><creatorcontrib>Morris, P F</creatorcontrib><creatorcontrib>Packer, L W</creatorcontrib><creatorcontrib>Raj, B</creatorcontrib><creatorcontrib>Rieth, M</creatorcontrib><creatorcontrib>Tran, M Q</creatorcontrib><creatorcontrib>Ward, D J</creatorcontrib><creatorcontrib>Zinkle, S J</creatorcontrib><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central (Alumni)</collection><collection>ProQuest Central UK/Ireland</collection><collection>ProQuest Central Essentials</collection><collection>AUTh Library subscriptions: ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Engineering Collection</collection><collection>Engineering Database</collection><collection>Publicly Available Content Database</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>ProQuest Central China</collection><collection>Engineering collection</collection><collection>arXiv.org</collection><jtitle>arXiv.org</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Stork, D</au><au>Agostini, P</au><au>J-L Boutard</au><au>Buckthorpe, D</au><au>Diegele, E</au><au>Dudarev, S L</au><au>English, C</au><au>Federici, G</au><au>Gilbert, M R</au><au>Gonzalez, S</au><au>Ibarra, A</au><au>Linsmeier, Ch</au><au>A Li Puma</au><au>Marbach, G</au><au>Morris, P F</au><au>Packer, L W</au><au>Raj, B</au><au>Rieth, M</au><au>Tran, M Q</au><au>Ward, D J</au><au>Zinkle, S J</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment</atitle><jtitle>arXiv.org</jtitle><date>2014-08-14</date><risdate>2014</risdate><eissn>2331-8422</eissn><abstract>The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a coherent strategy for R&D up to a DEMO construction decision. Technical consequences for the materials required and the development, testing and modelling programmes, are analysed using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants; and a project-based risk analysis, with R&D to mitigate risks from material shortcomings including development of specific risk mitigation materials.</abstract><cop>Ithaca</cop><pub>Cornell University Library, arXiv.org</pub><doi>10.48550/arxiv.1408.3546</doi><oa>free_for_read</oa></addata></record> |
fulltext | fulltext |
identifier | EISSN: 2331-8422 |
ispartof | arXiv.org, 2014-08 |
issn | 2331-8422 |
language | eng |
recordid | cdi_arxiv_primary_1408_3546 |
source | arXiv.org; Free E- Journals |
subjects | Coolants Electric power generation Functional materials Heat flux Heat transfer Inspection Nuclear power plants Physics - Instrumentation and Detectors R&D Research & development Risk analysis Systems engineering |
title | Developing Structural, High-heat flux and Plasma Facing Materials for a near-term DEMO Fusion Power Plant: the EU Assessment |
url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-24T22%3A12%3A11IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_arxiv&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Developing%20Structural,%20High-heat%20flux%20and%20Plasma%20Facing%20Materials%20for%20a%20near-term%20DEMO%20Fusion%20Power%20Plant:%20the%20EU%20Assessment&rft.jtitle=arXiv.org&rft.au=Stork,%20D&rft.date=2014-08-14&rft.eissn=2331-8422&rft_id=info:doi/10.48550/arxiv.1408.3546&rft_dat=%3Cproquest_arxiv%3E2084591459%3C/proquest_arxiv%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2084591459&rft_id=info:pmid/&rfr_iscdi=true |