Assessment of materials data for blanket materials within the European contribution to ITER

S. Wikman; A. Peacock; O. Zlamal; J. Öijerholm; Seppo Tähtinen; M. Rödig; P. Marmy; O. Gillia; P. Lorenzetto; S. Heikkinen

doi:10.1016/j.jnucmat.2013.03.028

Assessment of materials data for blanket materials within the European contribution to ITER

S. Wikman^*
, A. Peacock
, O. Zlamal
, J. Öijerholm
, Seppo Tähtinen
, M. Rödig
, P. Marmy
, O. Gillia
, P. Lorenzetto
, S. Heikkinen

^*Corresponding author for this work

Fusion for Energy (F4E)
Max-Planck-Institut für Plasmaphysik (IPP)
Research Centre Řež
Studsvik AB
Forschungszentrum Jülich GmbH (FZJ)
Paul Scherrer Institute (PSI)
Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)

Research output: Contribution to journal › Article › Scientific › peer-review

6 Citations (Scopus)

Abstract

In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been performed to ensure that requirements are fulfilled for the ITER operational conditions with acceptable margins for the foreseen lifetime of the ITER project. This paper will provide an overview of this qualification program with examples of recent results within the scope of the European contribution of blanket components to ITER. Ongoing actions to achieve a comprehensive understanding of the three main materials, beryllium, CuCrZr and stainless steel grade 316L(N)-IG, and their joints included in the blankets are discussed.

Original language	English
Pages (from-to)	S414-S419
Journal	Journal of Nuclear Materials
Volume	442
Issue number	Supplement
DOIs	https://doi.org/10.1016/j.jnucmat.2013.03.028
Publication status	Published - 2013
MoE publication type	A1 Journal article-refereed
Event	Fifteenth International Conference on Fusion Reactor Materials - Charleston, United States Duration: 16 Oct 2011 → 22 Oct 2011

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

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10.1016/j.jnucmat.2013.03.028

Cite this

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title = "Assessment of materials data for blanket materials within the European contribution to ITER",

abstract = "In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been performed to ensure that requirements are fulfilled for the ITER operational conditions with acceptable margins for the foreseen lifetime of the ITER project. This paper will provide an overview of this qualification program with examples of recent results within the scope of the European contribution of blanket components to ITER. Ongoing actions to achieve a comprehensive understanding of the three main materials, beryllium, CuCrZr and stainless steel grade 316L(N)-IG, and their joints included in the blankets are discussed.",

author = "S. Wikman and A. Peacock and O. Zlamal and J. {\"O}ijerholm and Seppo T{\"a}htinen and M. R{\"o}dig and P. Marmy and O. Gillia and P. Lorenzetto and S. Heikkinen",

year = "2013",

doi = "10.1016/j.jnucmat.2013.03.028",

language = "English",

volume = "442",

pages = "S414--S419",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "Supplement",

note = "Fifteenth International Conference on Fusion Reactor Materials, ICFRM-15 ; Conference date: 16-10-2011 Through 22-10-2011",

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TY - JOUR

T1 - Assessment of materials data for blanket materials within the European contribution to ITER

AU - Wikman, S.

AU - Peacock, A.

AU - Zlamal, O.

AU - Öijerholm, J.

AU - Tähtinen, Seppo

AU - Rödig, M.

AU - Marmy, P.

AU - Gillia, O.

AU - Lorenzetto, P.

AU - Heikkinen, S.

PY - 2013

Y1 - 2013

N2 - In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been performed to ensure that requirements are fulfilled for the ITER operational conditions with acceptable margins for the foreseen lifetime of the ITER project. This paper will provide an overview of this qualification program with examples of recent results within the scope of the European contribution of blanket components to ITER. Ongoing actions to achieve a comprehensive understanding of the three main materials, beryllium, CuCrZr and stainless steel grade 316L(N)-IG, and their joints included in the blankets are discussed.

AB - In recent years, material development for ITER blanket components has been fervent; yet, a lack of materials data has been identified by the ITER International Organization (IO) and other ITER parties. Therefore, extensive work on assessment of materials data and qualification of the materials with all the relevant interfaces (joints) has been performed to ensure that requirements are fulfilled for the ITER operational conditions with acceptable margins for the foreseen lifetime of the ITER project. This paper will provide an overview of this qualification program with examples of recent results within the scope of the European contribution of blanket components to ITER. Ongoing actions to achieve a comprehensive understanding of the three main materials, beryllium, CuCrZr and stainless steel grade 316L(N)-IG, and their joints included in the blankets are discussed.

U2 - 10.1016/j.jnucmat.2013.03.028

DO - 10.1016/j.jnucmat.2013.03.028

M3 - Article

SN - 0022-3115

VL - 442

SP - S414-S419

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - Supplement

T2 - Fifteenth International Conference on Fusion Reactor Materials

Y2 - 16 October 2011 through 22 October 2011

ER -

Assessment of materials data for blanket materials within the European contribution to ITER

Abstract

UN SDGs

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