JET contribution to ITER fuel cycle issues

C. Grisolia; N. Bekris; Jari Likonen; P. Coad; A. Semerok; D. Brennan; G. Piazza; S. Rosanvallon; JET-EFDA Contributors

doi:10.1016/j.fusengdes.2005.06.035

JET contribution to ITER fuel cycle issues

C. Grisolia (Corresponding Author), N. Bekris, Jari Likonen, P. Coad, A. Semerok, D. Brennan, G. Piazza, S. Rosanvallon, JET-EFDA Contributors

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

Abstract

The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and Be, which makes it best suited to study ITER relevant issues. A large variety of activities are performed within the JET fusion technology task force. In this paper, some topics, such as erosion/deposition and material transport, flakes characterization and detritiation techniques, are highlighted. Recent results obtained using a pumping cryopanel and on plasma facing component (PFC) characterization, are given. Finally, issues that will be addressed in the forthcoming JET work-programme are presented, such as a beryllium main wall for JET and in situ laser detritiation.

Original language	English
Pages (from-to)	679 - 683
Number of pages	5
Journal	Fusion Engineering and Design
Volume	75-79
DOIs	https://doi.org/10.1016/j.fusengdes.2005.06.035
Publication status	Published - 2005
MoE publication type	A1 Journal article-refereed

Keywords

detritiation techniques
fusion cycle
ITER
JET
fusion energy

UN SDGs

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

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10.1016/j.fusengdes.2005.06.035

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title = "JET contribution to ITER fuel cycle issues",

abstract = "The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and Be, which makes it best suited to study ITER relevant issues. A large variety of activities are performed within the JET fusion technology task force. In this paper, some topics, such as erosion/deposition and material transport, flakes characterization and detritiation techniques, are highlighted. Recent results obtained using a pumping cryopanel and on plasma facing component (PFC) characterization, are given. Finally, issues that will be addressed in the forthcoming JET work-programme are presented, such as a beryllium main wall for JET and in situ laser detritiation.",

keywords = "detritiation techniques, fusion cycle, ITER, JET, fusion energy",

author = "C. Grisolia and N. Bekris and Jari Likonen and P. Coad and A. Semerok and D. Brennan and G. Piazza and S. Rosanvallon and {JET-EFDA Contributors}",

year = "2005",

doi = "10.1016/j.fusengdes.2005.06.035",

language = "English",

volume = "75-79",

pages = "679 -- 683",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier B.V.",

}

TY - JOUR

T1 - JET contribution to ITER fuel cycle issues

AU - Grisolia, C.

AU - Bekris, N.

AU - Likonen, Jari

AU - Coad, P.

AU - Semerok, A.

AU - Brennan, D.

AU - Piazza, G.

AU - Rosanvallon, S.

AU - JET-EFDA Contributors,

PY - 2005

Y1 - 2005

N2 - The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and Be, which makes it best suited to study ITER relevant issues. A large variety of activities are performed within the JET fusion technology task force. In this paper, some topics, such as erosion/deposition and material transport, flakes characterization and detritiation techniques, are highlighted. Recent results obtained using a pumping cryopanel and on plasma facing component (PFC) characterization, are given. Finally, issues that will be addressed in the forthcoming JET work-programme are presented, such as a beryllium main wall for JET and in situ laser detritiation.

AB - The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and Be, which makes it best suited to study ITER relevant issues. A large variety of activities are performed within the JET fusion technology task force. In this paper, some topics, such as erosion/deposition and material transport, flakes characterization and detritiation techniques, are highlighted. Recent results obtained using a pumping cryopanel and on plasma facing component (PFC) characterization, are given. Finally, issues that will be addressed in the forthcoming JET work-programme are presented, such as a beryllium main wall for JET and in situ laser detritiation.

KW - detritiation techniques

KW - fusion cycle

KW - ITER

KW - JET

KW - fusion energy

U2 - 10.1016/j.fusengdes.2005.06.035

DO - 10.1016/j.fusengdes.2005.06.035

M3 - Article

SN - 0920-3796

VL - 75-79

SP - 679

EP - 683

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

JET contribution to ITER fuel cycle issues

Abstract

Keywords

UN SDGs

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