A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices

Nobuaki Noda; Volker Philipps; Rudolf Neu

doi:10.1016/s0022-3115(97)80042-6

A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices

Nobuaki Noda
, Volker Philipps
, Rudolf Neu

National Institutes of Natural Sciences - National Institute for Fusion Science
Forschungszentrum Jülich (FZJ)
Max Planck Institute for Plasma Physics

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

12 Scopus citations

Abstract

Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/re-deposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests, etc. An interim review of these studies is given. Tentative conclusions are drawn in order to gel a view and direction in the future studies.

Original language	English
Pages (from-to)	227-243
Number of pages	17
Journal	Journal of Nuclear Materials
Volume	241-243
DOIs	https://doi.org/10.1016/s0022-3115(97)80042-6
State	Published - 11 Feb 1997
Externally published	Yes

UN SDGs

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

SDG 7 Affordable and Clean Energy

Keywords

Erosion and particle deposition
High Z wall material
Impurity source
Impurity transport
Tritium inventory

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10.1016/s0022-3115(97)80042-6

Cite this

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title = "A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices",

abstract = "Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/re-deposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests, etc. An interim review of these studies is given. Tentative conclusions are drawn in order to gel a view and direction in the future studies.",

keywords = "Erosion and particle deposition, High Z wall material, Impurity source, Impurity transport, Tritium inventory",

author = "Nobuaki Noda and Volker Philipps and Rudolf Neu",

note = "Funding Information: (SNLL), J. Brooks (ANL), T. Tanabe (Nagoya Univ.), Y. Ueda (Osaka Univ.), M. Wada (Doshisha Univ.), K. Ohya (Tokushima Univ.), N. Yoshida (Kyushu Univ.), J. Winter (KFA Jiilich) and A. Grosman (CEA Cadarche) for giving valuable information, data and comments. One of the authors (N.N.) is indebted to the Ministry of Education, Science and Culture of Japan for the support by the Grant-in-Aid for scientific research (No. 05044115).",

year = "1997",

month = feb,

day = "11",

doi = "10.1016/s0022-3115(97)80042-6",

language = "English",

volume = "241-243",

pages = "227--243",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

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T1 - A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices

AU - Noda, Nobuaki

AU - Philipps, Volker

AU - Neu, Rudolf

N1 - Funding Information: (SNLL), J. Brooks (ANL), T. Tanabe (Nagoya Univ.), Y. Ueda (Osaka Univ.), M. Wada (Doshisha Univ.), K. Ohya (Tokushima Univ.), N. Yoshida (Kyushu Univ.), J. Winter (KFA Jiilich) and A. Grosman (CEA Cadarche) for giving valuable information, data and comments. One of the authors (N.N.) is indebted to the Ministry of Education, Science and Culture of Japan for the support by the Grant-in-Aid for scientific research (No. 05044115).

PY - 1997/2/11

Y1 - 1997/2/11

N2 - Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/re-deposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests, etc. An interim review of these studies is given. Tentative conclusions are drawn in order to gel a view and direction in the future studies.

AB - Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/re-deposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests, etc. An interim review of these studies is given. Tentative conclusions are drawn in order to gel a view and direction in the future studies.

KW - Erosion and particle deposition

KW - High Z wall material

KW - Impurity source

KW - Impurity transport

KW - Tritium inventory

UR - https://www.scopus.com/pages/publications/85051205977

U2 - 10.1016/s0022-3115(97)80042-6

DO - 10.1016/s0022-3115(97)80042-6

M3 - Article

AN - SCOPUS:85051205977

SN - 0022-3115

VL - 241-243

SP - 227

EP - 243

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices

Abstract

UN SDGs

Keywords

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