Design of a beam dump for the IFMIF-EVEDA accelerator

Brañas, B.; Iglesias, Daniel; Arranz, F.; Barrera, G.; Casal, N.; García, M.; Gómez, J. M. G.; López, Daniel; Martínez, Juana; Martín-Fuertes, F.; Ogando, F.; Oliver, C.; Sanz, J.; Sauvan, P.; Ibarra, Á.

doi:10.1016/j.fusengdes.2008.12.078

Cited by 23 publications

(10 citation statements)

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“…The HEBT line transports the beam from the Linac to the beam dump includes a Diagnostics Plate for beam characterization, a bending magnet to reduce the neutron radiation from beam dump towards upstream components, a magnetic beam expander to limit the power density on the beam dump (< 200 kW/cm 2 ), a lead shutter, closed during beam shutdown to act as a gamma shield from the activated beam dump and a beam scraper to protect the last portion of the vacuum pipe in front of the beam dump (see figure 13) [32]. A conical dump [33] made of copper has been designed to stop the 1.125 MW deuteron beam (see figure 14).…”

Section: The High Energy Beam Transport Lines (Hebt) and The Beam Dumpmentioning

confidence: 99%

IFMIF: overview of the validation activities

Knaster¹,

Arbeiter

Cara³

et al. 2013

Nucl. Fusion

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Abstract. The Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF), an international collaboration under the Broader Approach Agreement between Japan Government and EURATOM, aims at allowing a rapid construction phase of IFMIF in due time with an understanding of cost involved. The three main facilities of IFMIF: 1) the Accelerator facility, 2) the Target facility and 3) the Test facility are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. By July 2013, the engineering design activities of IFMIF matured with the delivery of an Intermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho (Japan). The world largest liquid Li test loop is running in Oarai (Japan) with an ambitious experimental programme for the years ahead. A full scale High Flux Test Module that will house ~1000 small specimens developed jointly in Europe and Japan for the Fusion programme has been constructed by KIT (Karlsruhe) together with its He gas cooling loop. A full scale Medium Flux Test Module to carry out on-line creep measurement has been constructed by CRPP (Villigen).

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Section: The High Energy Beam Transport Lines (Hebt) and The Beam Dumpmentioning

confidence: 99%

IFMIF: overview of the validation activities

Knaster¹,

Arbeiter

Cara³

et al. 2013

Nucl. Fusion

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“…1). This shape is adequate for the almost axis-symmetric IFMIF-EVEDA beam [3]. The resulting beam power deposition profile ( Fig.…”

Section: Beam Shape and Geometry Of Beam-facing Wallmentioning

confidence: 91%

“…The temperature, thermal gradients and stress fields in the beam dump material are directly dependant on the power density profile [2]. As the power density increases, the design of the beam dump becomes more complex.…”

Section: Beam Shape and Geometry Of Beam-facing Wallmentioning

confidence: 99%

The IFMIF-EVEDA accelerator beam dump design

Iglesias

Arranz

Alguacil

et al. 2011

Journal of Nuclear Materials

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ARTICLE INFO ABSTRACT Article history:Available online xxxxThe IFMIF-EVEDA accelerator will be a 9 MeV, 125 mAcw deuteron accelerator prototype for verifying the validity of the 40 MeV accelerator design for IFMIF. A beam dump designed for máximum power of 1.12 MW will be used to stop the beam at the accelerator exit. The conceptual design for the IFMIF-EVEDA accelerator beam dump is based on a conical beam stop made of OFE copper. The cooling system uses an axial high velocity flow of water pressurized up to 3.4 x 10 5 Pa to avoid boiling. The design has been shown to be compliant with ASME mechanical design rules under nominal full power conditions. A sensitivity analysis has been performed to take into account the possible margin on the beam properties at the beam dump entrance. This analysis together with the study of the maintenance issues and the mounting and dismounting operations has led to the complete design definition.

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“…The deuteron losses occurring along the beam tube (1 W/m) will not be considered here, taking into account those given in Table 1 [2,3]). The components considered to be activated are those mentioned above except ion source/injector and LEBT.…”

Section: Introductionmentioning

confidence: 99%