SiC/SiC composite heater for IFMIF

Abe, Takahiro; Kishimoto, Hirotatsu; Nakazato, Naofumi; Park, J.S.; Jung, Huicheul; Kohno, Yutaka

doi:10.1016/j.fusengdes.2012.02.124

Cited by 11 publications

(4 citation statements)

References 10 publications

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“…Design work of the test facilities is accompanied by prototyping of the High Flux Test Module (HFTM) and internal rigs for post-irradiation examination of miniature-size specimens of fusion reactor materials and online creep testing in the Medium Flux Test Module (CFTM). It is also making progress on the design and R&D of an alternative proposal of HFTM, potentially enabling irradiation under very high temperatures, adequate for irradiation testing of SiC [16].…”

Section: Test Facility Validation Activitiesmentioning

confidence: 99%

“…• an Accelerator Prototype (LIPAc) at Rokkasho, fully representative of the IFMIF low energy (9 MeV) accelerator (125 mA of D + beam in continuous wave) to be completed in June 2017 [10,11]; • a lithium test loop (ELTL) at Oarai, integrating all elements of the IFMIF lithium target facility, already commissioned in February 2011 [12,13] complemented by corrosion experiments performed at the LIFUS6 lithium loop at Brasimone [14]; • the high flux test module (HFTM) (different designs) [15,16] and its internals to be irradiated in a fission reactor [17] and tested in the helium loop HELOKA [18] complemented by the creep-fatigue test module (CFTM) [19] manufactured and tested in full scale at Villigen.…”

Section: Ifmif Validation Activitiesmentioning

confidence: 99%

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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: Test Facility Validation Activitiesmentioning

confidence: 99%

Section: Ifmif Validation Activitiesmentioning

confidence: 99%

IFMIF: overview of the validation activities

Knaster¹,

Arbeiter

Cara³

et al. 2013

Nucl. Fusion

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show abstract

“…IFMIF presents three technological challenges that the EVEDA phase aims to overcome: (1) the Accelerator Facility, (2) the Target Facility, and (3) the Test Facility. Three major prototypes have been designed and are either presently operating or being manufactured: (1) an Accelerator Prototype (LIPAc) at Rokkasho, cloning those of IFMIF up to its first superconductive accelerating stage (9 MeV energy, 125 mA of D + continuous wave current) to be completed in June 2017 [22]; (2) a Li Test Loop (ELTL) at Oarai, integrating all elements of the IFMIF Li Target Facility, commissioned in February 2011 [23], complemented by corrosion experiments performed at a Li loop (Lifus6) in Brasimone [24]; and (3) the High Flux Test Module (two different designs to accommodate either RAFM or SiC) [25,26] with a prototype of the capsules housing the small specimens to be irradiated in the BR2 fission reactor of SCK/CEN Mol [27] and tested in the cooling helium loop HELOKA of KIT, Karlsruhe [28]; complemented with the Creep Fatigue Test Module [29] manufactured and tested in full scale at PSI, Villigen. The validation activities and its most recent status have been described elsewhere [20][21][22].…”

Section: Status Of Validation Activitiesmentioning

confidence: 99%

IFMIF, a fusion relevant neutron source for material irradiation current status

Knaster¹,

Chel

Fischer

et al. 2014

Journal of Nuclear Materials

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“…Due to their thermophysical and nuclear properties, refractory ceramics are attractive materials for applications in future nuclear power reactors (fusion [1][2][3] or fission concepts [3,4]) [5]. Since the Fukushima accident, ceramic cladding has been the subject of substantial research as it could offer improved safety and performance as well as addressing the current problems with zirconium alloy cladding in light water reactors (LWRs) [6][7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%