Overview of results of the first phase of validation activities for the IFMIF High Flux Test Module

Arbeiter, Frederik; Chen, Yuming; Dolensky, B.; Freund, J.; Heupel, T.; Klein, Christine A.; Scheel, Nicola; Schlindwein, Georg

doi:10.1016/j.fusengdes.2012.03.045

Cited by 18 publications

(11 citation statements)

References 6 publications

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“…The main technological challenges will be overcome upon the termination of the BA Agreement by mid-2017, thanks to the construction and validation of cleverly chosen prototypes, even at full scale and performance. Although the validation activities were not fully accomplished at the time of the release of the IFMIF Intermediate Engineering Design Report (IIEDR), their maturity [16,21,24,25,28,33,36] allows entering with confidence into the Construction, Operation and Decommissioning Activities (CODA) phase.…”

Section: Discussionmentioning

confidence: 99%

“…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%

“…A High Flux Test Module (HFTM) capable to irradiate specimens at temperatures ranging between 250°C and 550°C with a maximum temperature spread of +/À3% within specimens inside one capsule is under fabrication in KIT [25]. The cooling system based on helium gas has been successfully validated in the HELOKA loop [28], and will be tested together with the full scale HFTM prototype.…”

Section: Status Of Validation Activitiesmentioning

confidence: 99%

See 2 more Smart Citations

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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Section: Discussionmentioning

confidence: 99%

Section: Status Of Validation Activitiesmentioning

confidence: 99%

Section: Status Of Validation Activitiesmentioning

confidence: 99%

See 1 more Smart Citation

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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“…The HFTM-V (see figure 19) is dedicated to the research on RAFM steels, to be tested in the temperature range 250-550 • C, with an option to provide irradiation up to 650 • C for oxide dispersion strengthened (ODS) steels [90]. The uncertainty of temperature for 80% of the specimens will be below ±3% thanks to an independent cooling of the capsules, which in addition count with an independent system of heaters, thermocouples and thermalisation of the specimens by filling the capsules with NaK-78 eutectic alloy.…”

Section: The Test Modulesmentioning

confidence: 99%

The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source

Knaster¹,

Ibarra

Abal

et al. 2015

Nucl. Fusion

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The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Desi gn Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF plant, which is here described. Many improvements of the design from former phases are implemented, particularly a reduction of beam losses and operational costs thanks to the superconducting accelerator concept, the re-location of the quench tank outside the 1 2 × test cell (TC) with a reduction of tritium inventory and a simplification on its replacement in case of failure, the separation of the irradiation modules from the shielding block gaining irradiation flexibility and enhancement of the remote handling equipment reliability and cost reduction, and the water cooling of the liner and biological shielding of the TC, enhancing the efficiency and economy of the related sub-systems. In addition, the maintenance strategy has been modified to allow a shorter yearly stop of the irradiation operations and a more careful management of the irradiated samples. The design of the IFMIF plant is intimately linked with the EVA phase carried out since the entry into force of IFMIF/EVEDA in June 2007. These last activities and their on-going accomplishment have been thoroughly described elsewhere (Knaster J et al [19]), which, combined with the present paper, allows a clear understanding of the maturity of the European-Japanese international efforts. This released IFMIF Intermediate Engineering Design Report (IIEDR), which could be complemented if required concurrently with the outcome of the on-going EVA, will allow decision making on its construction and/or serve as the basis for the definition of the next step, aligned with the evolving needs of our fusion community.

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“…In this framework is where IFMIF-DONES (DEMO oriented neutron source) [21][22][23] plays an important role in order to test materials under similar neutron nuclear fusion irradiation condition. But, as the irradiation requirements of high flux test module (HFTM) [24][25][26][27] of IFMIF-DONES were designed to reproduce the nuclear fusion irradiation condition for EUROFER samples, in this work the potential use of the HFTM to test Cu-alloys and W under similar nuclear fusion irradiation conditions is addressed, i.e. to verify whether design equivalent nuclear fusion irradiation condition is possible.…”

Section: Introductionmentioning

confidence: 99%