Review on the EFDA programme on tungsten materials technology and science

M. Rieth; J.L. Boutard; S.L. Dudarev; T. Ahlgren; S. Antusch; N. Baluc; M.-F. Barthe; C.S. Becquart; L. Ciupinski; J.B. Correia; C. Domain; J. Fikar; E. Fortuna; C.C. Fu; E. Gaganidze; T.L. Galan; C. Garcia-Rosales; B. Gludovatz; H. Greuner; K. Heinola; N. Holstein; N. Juslin; F. Koch; W. Krauss; K.J. Kurzydlowski; J. Linke; Ch. Linsmeier; N. Luzginova; H. Maier; M.S. Martinez; J.M. Missiaen; M. Muhammed; A. Munoz; M. Muzyk; K. Nordlund; D. Nguyen-Manh; P. Norajitra; J. Opschoor; G. Pintsuk; R. Pippan; G. Ritz; L. Romaner; D. Rupp; R. Schaublin; J. Schlosser; Inge Uytdenhouwen; J.G. van der Laan; L. Veleva; L. Ventelon; S. Wahlberg; F. Williaime; S. Wurster; M.A. Yar; Vincent Massaut

doi:10.1016/j.jnucmat.2011.01.075

Review on the EFDA programme on tungsten materials technology and science

M. Rieth, J.L. Boutard, S.L. Dudarev, T. Ahlgren, S. Antusch, N. Baluc, M.-F. Barthe, C.S. Becquart, L. Ciupinski, J.B. Correia, C. Domain, J. Fikar, E. Fortuna, C.C. Fu, E. Gaganidze, T.L. Galan, C. Garcia-Rosales, B. Gludovatz, H. Greuner, K. HeinolaN. Holstein, N. Juslin, F. Koch, W. Krauss, K.J. Kurzydlowski, J. Linke, Ch. Linsmeier, N. Luzginova, H. Maier, M.S. Martinez, J.M. Missiaen, M. Muhammed, A. Munoz, M. Muzyk, K. Nordlund, D. Nguyen-Manh, P. Norajitra, J. Opschoor, G. Pintsuk, R. Pippan, G. Ritz, L. Romaner, D. Rupp, R. Schaublin, J. Schlosser, Inge Uytdenhouwen, J.G. van der Laan, L. Veleva, L. Ventelon, S. Wahlberg, F. Williaime, S. Wurster, M.A. Yar, Vincent Massaut

Research output › peer-review

Abstract

All the recent DEMO design studies for helium cooled divertors utilize tungsten materials and alloys, mainly due to their high temperature strength, good thermal conductivity, low erosion, and comparably low activation under neutron irradiation. The long-term objective of the EFDA fusion materials programme is to develop structural as well as armor materials in combination with the necessary production and fabrication technologies for future divertor concepts. The programmatic roadmap is structured into four engineering research lines which comprise fabrication process development, structural material development, armor material optimization, and irradiation performance testing, which are complemented by a fundamental research programme on ‘‘Materials Science and Modeling’’. This paper presents the current research status of the EFDA experimental and testing investigations, and gives a detailed overview of the latest results on fabrication, joining, high heat flux testing, plasticity, modeling, and validation experiments.

Original language	English
Pages (from-to)	463-467
Journal	Journal of Nuclear Materials
Volume	417
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2011.01.075
State	Published - Feb 2011
Event	ICFRM14 2009 - 14th International Conference on Fusion Reactor Materials - Japan - IAEA, Sapporo Duration: 7 Sep 2009 → 12 Sep 2009

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Cite this

Rieth, M., Boutard, J. L., Dudarev, S. L., Ahlgren, T., Antusch, S., Baluc, N., Barthe, M.-F., Becquart, C. S., Ciupinski, L., Correia, J. B., Domain, C., Fikar, J., Fortuna, E., Fu, C. C., Gaganidze, E., Galan, T. L., Garcia-Rosales, C., Gludovatz, B., Greuner, H., ... Massaut, V. (2011). Review on the EFDA programme on tungsten materials technology and science. Journal of Nuclear Materials, 417(1-3), 463-467. https://doi.org/10.1016/j.jnucmat.2011.01.075

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title = "Review on the EFDA programme on tungsten materials technology and science",

abstract = "All the recent DEMO design studies for helium cooled divertors utilize tungsten materials and alloys, mainly due to their high temperature strength, good thermal conductivity, low erosion, and comparably low activation under neutron irradiation. The long-term objective of the EFDA fusion materials programme is to develop structural as well as armor materials in combination with the necessary production and fabrication technologies for future divertor concepts. The programmatic roadmap is structured into four engineering research lines which comprise fabrication process development, structural material development, armor material optimization, and irradiation performance testing, which are complemented by a fundamental research programme on {\textquoteleft}{\textquoteleft}Materials Science and Modeling{\textquoteright}{\textquoteright}. This paper presents the current research status of the EFDA experimental and testing investigations, and gives a detailed overview of the latest results on fabrication, joining, high heat flux testing, plasticity, modeling, and validation experiments.",

keywords = "Fusion, DEMO, Tungsten",

author = "M. Rieth and J.L. Boutard and S.L. Dudarev and T. Ahlgren and S. Antusch and N. Baluc and M.-F. Barthe and C.S. Becquart and L. Ciupinski and J.B. Correia and C. Domain and J. Fikar and E. Fortuna and C.C. Fu and E. Gaganidze and T.L. Galan and C. Garcia-Rosales and B. Gludovatz and H. Greuner and K. Heinola and N. Holstein and N. Juslin and F. Koch and W. Krauss and K.J. Kurzydlowski and J. Linke and Ch. Linsmeier and N. Luzginova and H. Maier and M.S. Martinez and J.M. Missiaen and M. Muhammed and A. Munoz and M. Muzyk and K. Nordlund and D. Nguyen-Manh and P. Norajitra and J. Opschoor and G. Pintsuk and R. Pippan and G. Ritz and L. Romaner and D. Rupp and R. Schaublin and J. Schlosser and Inge Uytdenhouwen and {van der Laan}, J.G. and L. Veleva and L. Ventelon and S. Wahlberg and F. Williaime and S. Wurster and M.A. Yar and Vincent Massaut",

note = "Score = 10; ICFRM14 2009 - 14th International Conference on Fusion Reactor Materials - Japan ; Conference date: 07-09-2009 Through 12-09-2009",

year = "2011",

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doi = "10.1016/j.jnucmat.2011.01.075",

language = "English",

volume = "417",

pages = "463--467",

journal = "Journal of Nuclear Materials",

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Rieth, M, Boutard, JL, Dudarev, SL, Ahlgren, T, Antusch, S, Baluc, N, Barthe, M-F, Becquart, CS, Ciupinski, L, Correia, JB, Domain, C, Fikar, J, Fortuna, E, Fu, CC, Gaganidze, E, Galan, TL, Garcia-Rosales, C, Gludovatz, B, Greuner, H, Heinola, K, Holstein, N, Juslin, N, Koch, F, Krauss, W, Kurzydlowski, KJ, Linke, J, Linsmeier, C, Luzginova, N, Maier, H, Martinez, MS, Missiaen, JM, Muhammed, M, Munoz, A, Muzyk, M, Nordlund, K, Nguyen-Manh, D, Norajitra, P, Opschoor, J, Pintsuk, G, Pippan, R, Ritz, G, Romaner, L, Rupp, D, Schaublin, R, Schlosser, J, Uytdenhouwen, I, van der Laan, JG, Veleva, L, Ventelon, L, Wahlberg, S, Williaime, F, Wurster, S, Yar, MA & Massaut, V 2011, 'Review on the EFDA programme on tungsten materials technology and science', Journal of Nuclear Materials, vol. 417, no. 1-3, pp. 463-467. https://doi.org/10.1016/j.jnucmat.2011.01.075

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AU - Rieth, M.

AU - Boutard, J.L.

AU - Dudarev, S.L.

AU - Ahlgren, T.

AU - Antusch, S.

AU - Baluc, N.

AU - Barthe, M.-F.

AU - Becquart, C.S.

AU - Ciupinski, L.

AU - Correia, J.B.

AU - Domain, C.

AU - Fikar, J.

AU - Fortuna, E.

AU - Fu, C.C.

AU - Gaganidze, E.

AU - Galan, T.L.

AU - Garcia-Rosales, C.

AU - Gludovatz, B.

AU - Greuner, H.

AU - Heinola, K.

AU - Holstein, N.

AU - Juslin, N.

AU - Koch, F.

AU - Krauss, W.

AU - Kurzydlowski, K.J.

AU - Linke, J.

AU - Linsmeier, Ch.

AU - Luzginova, N.

AU - Maier, H.

AU - Martinez, M.S.

AU - Missiaen, J.M.

AU - Muhammed, M.

AU - Munoz, A.

AU - Muzyk, M.

AU - Nordlund, K.

AU - Nguyen-Manh, D.

AU - Norajitra, P.

AU - Opschoor, J.

AU - Pintsuk, G.

AU - Pippan, R.

AU - Ritz, G.

AU - Romaner, L.

AU - Rupp, D.

AU - Schaublin, R.

AU - Schlosser, J.

AU - Uytdenhouwen, Inge

AU - van der Laan, J.G.

AU - Veleva, L.

AU - Ventelon, L.

AU - Wahlberg, S.

AU - Williaime, F.

AU - Wurster, S.

AU - Yar, M.A.

A2 - Massaut, Vincent

N1 - Score = 10

PY - 2011/2

Y1 - 2011/2

N2 - All the recent DEMO design studies for helium cooled divertors utilize tungsten materials and alloys, mainly due to their high temperature strength, good thermal conductivity, low erosion, and comparably low activation under neutron irradiation. The long-term objective of the EFDA fusion materials programme is to develop structural as well as armor materials in combination with the necessary production and fabrication technologies for future divertor concepts. The programmatic roadmap is structured into four engineering research lines which comprise fabrication process development, structural material development, armor material optimization, and irradiation performance testing, which are complemented by a fundamental research programme on ‘‘Materials Science and Modeling’’. This paper presents the current research status of the EFDA experimental and testing investigations, and gives a detailed overview of the latest results on fabrication, joining, high heat flux testing, plasticity, modeling, and validation experiments.

AB - All the recent DEMO design studies for helium cooled divertors utilize tungsten materials and alloys, mainly due to their high temperature strength, good thermal conductivity, low erosion, and comparably low activation under neutron irradiation. The long-term objective of the EFDA fusion materials programme is to develop structural as well as armor materials in combination with the necessary production and fabrication technologies for future divertor concepts. The programmatic roadmap is structured into four engineering research lines which comprise fabrication process development, structural material development, armor material optimization, and irradiation performance testing, which are complemented by a fundamental research programme on ‘‘Materials Science and Modeling’’. This paper presents the current research status of the EFDA experimental and testing investigations, and gives a detailed overview of the latest results on fabrication, joining, high heat flux testing, plasticity, modeling, and validation experiments.

KW - Fusion

KW - DEMO

KW - Tungsten

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_115850

UR - http://knowledgecentre.sckcen.be/so2/bibref/8306

U2 - 10.1016/j.jnucmat.2011.01.075

DO - 10.1016/j.jnucmat.2011.01.075

M3 - Article

SN - 0022-3115

VL - 417

SP - 463

EP - 467

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

T2 - ICFRM14 2009 - 14th International Conference on Fusion Reactor Materials - Japan

Y2 - 7 September 2009 through 12 September 2009

ER -