Fuel retention studies with the ITER-Like Wall in JET

被引：188

作者：

Brezinsek, S. ^{[1
,2
]}

Loarer, T. ^{[1
,3
]}

Philipps, V. ^{[1
,2
]}

Esser, H. G. ^{[1
,2
]}

Gruenhagen, S. ^{[1
,4
]}

Smith, R. ^{[1
,4
]}

Felton, R. ^{[1
,4
]}

Banks, J. ^{[1
,4
]}

Belo, P. ^{[1
,5
]}

Boboc, A. ^{[1
,4
]}

Bucalossi, J. ^{[1
,3
]}

Clever, M. ^{[1
,2
]}

Coenen, J. W. ^{[1
,2
]}

Coffey, I. ^{[1
,6
]}

Devaux, S. ^{[1
,9
]}

Douai, D. ^{[1
,3
]}

Freisinger, M. ^{[1
,3
]}

Frigione, D. ^{[1
,7
]}

Groth, M. ^{[1
,8
]}

Huber, A. ^{[1
,2
]}

Hobirk, J. ^{[1
,9
]}

Jachmich, S. ^{[1
,10
]}

Knipe, S. ^{[1
,4
]}

Krieger, K. ^{[1
,9
]}

Kruezi, U. ^{[1
,3
]}

Marsen, S. ^{[1
,9
]}

Matthews, G. F. ^{[1
,4
]}

Meigs, A. G. ^{[1
,4
]}

Nave, F. ^{[1
,5
]}

Nunes, I. ^{[1
,5
]}

Neu, R. ^{[1
,9
]}

Roth, J. ^{[1
,9
]}

Stamp, M. F. ^{[1
]}

Vartanian, S. ^{[1
,3
]}

Samm, U. ^{[1
,2
]}

机构：

[1] Culham Sci Ctr, JET EFDA, Abingdon OX14 3DB, Oxon, England

[2] Forschungszentrum Julich, Assoc EURATOM FZJ, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany

[3] CEA, IRFM, F-13108 St Paul Les Durance, France

[4] Culham Sci Ctr, EURATOM CCFE Fus Assoc, Abingdon OX14 3DB, Oxon, England

[5] Assoc EURATOM IST, Inst Plasmas & Nucl Fus, Lisbon, Portugal

[6] Queens Univ Belfast, Belfast BT7 1NN, Antrim, North Ireland

[7] Assoc EURATOM ENEA Fusi, Rome, Italy

[8] Aalto Univ, Assoc EURATOM Tekes, Espoo, Finland

[9] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany

[10] ERM KMS, Assoc Euratom Etat Belge, Brussels, Belgium

来源：

NUCLEAR FUSION | 2013年 / 53卷 / 08期

关键词：

DEUTERIUM; BALANCE; RELEASE;

D O I：

10.1088/0029-5515/53/8/083023

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

JET underwent a transformation from a full carbon-dominated tokamak to a fully metallic device with beryllium in the main chamber and a tungsten divertor. This material combination is foreseen for the activated phase of ITER. The ITER-Like Wall (ILW) experiment at JET shall demonstrate the plasma compatibility with metallic walls and the reduction in fuel retention. We report on a set of experiments (I-p = 2.0 MA, B-t = 2.0-2.4 T, delta = 0.2-0.4) in different confinement and plasma conditions with global gas balance analysis demonstrating a strong reduction in the long-term retention rate by more than a factor of 10 with respect to carbon-wall reference discharges. All experiments are executed in a series of identical plasma discharges in order to achieve maximum plasma duration until the analysis limit of the active gas handling system is reached. The composition analysis shows high purity of the recovered gas, typically 99% D. For typical L-mode discharges (P-aux = 0.5 MW), type III (P-aux = 5.0 MW) and type-I ELMy H-mode plasmas (P-aux = 12.0 MW) a drop of the deuterium retention rate normalized to the operational time in divertor configuration is measured from 1.27 x 10(21), 1.37 x 10(21) and 1.97 x 10(21) Ds(-1) down to 4.8 x 10(19), 7.2 x 10(19) and 16 x 10(19) Ds(-1), respectively. The dynamic retention increases in the limiter phase in comparison with carbon-fibre composite, but also the outgassing after the discharge has risen in the same manner and overcompensates this transient retention. Overall an upper limit of the long-term retention rate of 1.5 x 10(20) Ds(-1) is obtained with the ILW. The observed reduction by one order of magnitude confirms the expected predictions concerning the plasma-facing material change in ITER and is in line with identification of fuel co-deposition with Be as the main mechanism for the residual long-term retention. The reduction widens the operational space without active cleaning in the DT phase in comparison with a full carbon device.

引用

页数：13

共 18 条

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