Impact of W on scenario simulations for ITER

ITPA Integrated Operating Scenarios Topical Group; ASDEX Upgrade Team; JET Contributors

doi:10.1088/0029-5515/55/6/063031

Impact of W on scenario simulations for ITER

ITPA Integrated Operating Scenarios Topical Group, ASDEX Upgrade Team, JET Contributors

Laboratory for Plasma Physics

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

Abstract

In preparation of ITER operation, large machines have replaced their wall and divertor material to W (ASDEX Upgrade) or a combination of Be for the wall and W for the divertor (JET). Operation in these machines has shown that the influx of W can have a significant impact on the discharge evolution, which has made modelling of this impact for ITER an urgent task. This paper reports on such modelling efforts. Maximum tolerable W concentrations have been determined for various scenarios, both for the current ramp-up and flat-top phase. Results of two independent methods are presented, based on the codes ZIMPUR plus ASTRA and CRONOS, respectively. Both methods have been tested and benchmarked against ITER-like I_p RU experiments at JET. It is found that W significantly disturbs the discharge evolution when the W concentration approaches ∼10^-4; this critical level varies somewhat between scenarios.

Original language	English
Article number	063031
Journal	Nuclear Fusion
Volume	55
Issue number	6
DOIs	https://doi.org/10.1088/0029-5515/55/6/063031
Publication status	Published - 1 Jun 2015

Keywords

52.25.Fi
52.25.Vy
52.55.Fa

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10.1088/0029-5515/55/6/063031

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title = "Impact of W on scenario simulations for ITER",

abstract = "In preparation of ITER operation, large machines have replaced their wall and divertor material to W (ASDEX Upgrade) or a combination of Be for the wall and W for the divertor (JET). Operation in these machines has shown that the influx of W can have a significant impact on the discharge evolution, which has made modelling of this impact for ITER an urgent task. This paper reports on such modelling efforts. Maximum tolerable W concentrations have been determined for various scenarios, both for the current ramp-up and flat-top phase. Results of two independent methods are presented, based on the codes ZIMPUR plus ASTRA and CRONOS, respectively. Both methods have been tested and benchmarked against ITER-like Ip RU experiments at JET. It is found that W significantly disturbs the discharge evolution when the W concentration approaches ∼10-4; this critical level varies somewhat between scenarios.",

keywords = "52.25.Fi, 52.25.Vy, 52.55.Fa",

author = "\{ITPA Integrated Operating Scenarios Topical Group\} and \{ASDEX Upgrade Team\} and \{JET Contributors\} and Hogeweij, \{G. M.D.\} and V. Leonov and J. Schweinzer and Sips, \{A. C.C.\} and C. Angioni and G. Calabr{\`o} and R. Dux and A. Kallenbach and E. Lerche and C. Maggi and Th P{\"u}tterich",

note = "Publisher Copyright: {\textcopyright} 2015 EURATOM.",

year = "2015",

month = jun,

day = "1",

doi = "10.1088/0029-5515/55/6/063031",

language = "English",

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T1 - Impact of W on scenario simulations for ITER

AU - ITPA Integrated Operating Scenarios Topical Group

AU - ASDEX Upgrade Team

AU - JET Contributors

AU - Hogeweij, G. M.D.

AU - Leonov, V.

AU - Schweinzer, J.

AU - Sips, A. C.C.

AU - Angioni, C.

AU - Calabrò, G.

AU - Dux, R.

AU - Kallenbach, A.

AU - Lerche, E.

AU - Maggi, C.

AU - Pütterich, Th

PY - 2015/6/1

Y1 - 2015/6/1

N2 - In preparation of ITER operation, large machines have replaced their wall and divertor material to W (ASDEX Upgrade) or a combination of Be for the wall and W for the divertor (JET). Operation in these machines has shown that the influx of W can have a significant impact on the discharge evolution, which has made modelling of this impact for ITER an urgent task. This paper reports on such modelling efforts. Maximum tolerable W concentrations have been determined for various scenarios, both for the current ramp-up and flat-top phase. Results of two independent methods are presented, based on the codes ZIMPUR plus ASTRA and CRONOS, respectively. Both methods have been tested and benchmarked against ITER-like Ip RU experiments at JET. It is found that W significantly disturbs the discharge evolution when the W concentration approaches ∼10-4; this critical level varies somewhat between scenarios.

AB - In preparation of ITER operation, large machines have replaced their wall and divertor material to W (ASDEX Upgrade) or a combination of Be for the wall and W for the divertor (JET). Operation in these machines has shown that the influx of W can have a significant impact on the discharge evolution, which has made modelling of this impact for ITER an urgent task. This paper reports on such modelling efforts. Maximum tolerable W concentrations have been determined for various scenarios, both for the current ramp-up and flat-top phase. Results of two independent methods are presented, based on the codes ZIMPUR plus ASTRA and CRONOS, respectively. Both methods have been tested and benchmarked against ITER-like Ip RU experiments at JET. It is found that W significantly disturbs the discharge evolution when the W concentration approaches ∼10-4; this critical level varies somewhat between scenarios.

KW - 52.25.Fi

KW - 52.25.Vy

KW - 52.55.Fa

UR - https://www.scopus.com/pages/publications/84935844828

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DO - 10.1088/0029-5515/55/6/063031

M3 - Article

AN - SCOPUS:84935844828

SN - 0029-5515

VL - 55

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 6

M1 - 063031

ER -

Impact of W on scenario simulations for ITER

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Keywords

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