Fusion Engineering and Design 88 (2013) 985–989
Contents lists available at ScienceDirect
Fusion Engineering and Design
journal h om epa ge: www.elsevier.com/locat e/fusengdes
Design status and procurement activities of the High Voltage Deck 1 and Bushing
for the ITER Neutral Beam Injector
Marco Boldrin
a,∗
, Antonio De Lorenzi
a
, Hans Decamps
c
, Luca Grando
a
, Muriel Simon
b
, Vanni Toigo
a
a
Consorzio RFX, Associazione EURATOM-ENEA sulla Fusione, Corso Stati Uniti 4, I-35127 Padova, Italy
b
Fusion For Energy, c/ Josep Pla 2, 08019 Barcelona, Spain
c
ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France
h i g h l i g h t s
◮ ITER Neutral Beam Injector includes several non-standard components.
◮ The design status of the -1 MV
dc
HVD1 and Bushing is described.
◮ The paper reports also on the integrated layout of the two components.
◮ Preliminary electrostatic and thermal analyses are presented.
◮ Procurement activities are outlined.
a r t i c l e i n f o
Article history:
Available online 6 March 2013
Keywords:
ITER
Neutral Beam Injector (NBI)
High Voltage Deck 1 (HVD1)
High Voltage Bushing
Insulation design
Thermal design
a b s t r a c t
The ITER Neutral Beam Injector (NBI) power supply system includes several non-standard components,
whose ratings go beyond the present industrial practice. Two of these items, to be procured by Fusion
for Energy, are:
1. A -1 MV
dc
air-insulated Faraday cage, called High Voltage Deck 1 (HVD1), hosting the Ion Source and
Extractor Power Supplies (ISEPS) and the associated diagnostics.
2. A -1 MV
dc
feedthrough, called HVD1-TL Bushing, aimed at connecting the HVD1 to the gas (SF
6
) insu-
lated Transmission Line (TL), containing inside its High Voltage (HV) conductor all ISEPS power and
control cables coming from the HVD1 to be connected to the NBI Ion Source services.
The paper deals with the status of the design of the HVD1 and HVD1-TL Bushing, focusing on insulation,
mechanical and thermal issues as well as on their integration with the other components of the power
supply system. In particular, the insulation issue of the integrated system has been addressed by means
of an electrostatic Finite Element (FE) analysis whilst a FE thermal simulation has been carried out to
assess the impact of the dissipation of the proposed design of the inner conductors (ISEPS conductors)
not actively cooled. Finally, the paper describes the status of procurement strategy and execution.
© 2013 Consorzio RFX Associazione Euratom ENEA sulla Fusione.
Published by Elsevier B.V. All rights reserved.
1. Introduction
In ITER the plasma burning conditions will be obtained and con-
trolled by means of two Neutral Beam Injectors (NBIs) – belonging
to the additional Heating and Current Drive systems – designed to
deliver up to 16.5 MW power of neutral particles (H or D) to the
Disclaimer: The views and opinions expressed herein do not necessarily reflect
those of the ITER Organization.
∗
Corresponding author. Tel.: +39 049 829 5681; fax: +39 049 870 0718.
E-mail address: marco.boldrin@igi.cnr.it (M. Boldrin).
plasma at 1 MeV of energy and with a pulse length up to 3600 s [1].
To optimize the NBI design and operation, a dedicated Test Facility
(PRIMA – Padua Research on Injectors with Megavolt Acceleration)
is under construction in Padua, Italy, at the Consorzio RFX premises.
PRIMA will host a full scale prototype of the ITER NBI (MITICA –
Megavolt ITER Injector & Concept Advancement) [2].
The ITER NBI and MITICA experiment include a complex power
supply system, represented by the simplified scheme of Fig. 1. The
whole Ion Source is polarized to ground at acceleration voltage
(-1012 kV
dc
); all the Ion Source services, i.e. the power supplies,
indicated as Ion Source and Extractor Power Supplies (ISEPS [3]),
and the cubicles for control and diagnostics shall be therefore
0920-3796/$ – see front matter © 2013 Consorzio RFX Associazione Euratom ENEA sulla Fusione. Published by Elsevier B.V. All rights reserved.
http://dx.doi.org/10.1016/j.fusengdes.2012.11.029