Overview of the IFMIF test facility design in IFMIF/EVEDA phase

Tian, Kuo; Abou-Sena, Ali; Arbeiter, Frederik; García, A. R.; Gouat, P.; Heidinger, R.; Heinzel, V.; Ibarra, Á.; Leysen, W.; Mas, Alicia; Mittwollen, Martin; Möslang, A.; Theile, J.; Yamamoto, M.; Yokomine, Takehiko

doi:10.1016/j.fusengdes.2015.05.041

Cited by 5 publications

(6 citation statements)

References 17 publications

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“…The HFTM-DC, full-scale prototype of the IFMIF's HFTM, was tested in the HELOKA loop of KIT [51] demonstrating the feasibility of reaching the uniformity of the temperature of the full stack of small specimens fitting in a capsule. Thus, it will be capable of characterizing a given material at the pre-set temperature within 250 °C < T < 550 °C, within ±3% during irradiation [23] (see section 3.4) [50].…”

Section: Discussionmentioning

confidence: 99%

“…This opening is closed during irradiation periods by two concrete shielding plugs (SPs) 2.5 m high in total. The inner walls of the TC are covered by a closed steel liner [23].…”

Section: Edasmentioning

confidence: 99%

“…The TF [23] includes the systems required to accommodate the TMs under a controlled environment and conditions for irradiation, as well as all the systems required for their assembly and disassembly and submission of the irradiated specimens to the PIEF. The TF comprises all equipment, primary heat removal systems, purge gas systems and handling facilities for an accurate and safe positioning and handling of specimen, modules, and target during beam operation and maintenance.…”

Section: The Test Facilitymentioning

confidence: 99%

“…The ΔT measured in the stack of small specimens thoroughly instrumented in the prototype rigs assembled in the HFTM-DC tested in the HELOKA-LP complied with the specified target ±3% in 97% of the capsule volume in the temperature range 250 °C < T < 550 °C [23,50,79]. Furthermore, three capsules filled with small specimens and thermalized with NaK were irradiated in the experimental reactor of SCK-CEN in Mol [50].…”

Section: Feasibility Of Irradiating the Small Specimens Under A Unifo...mentioning

confidence: 99%

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Overview of the IFMIF/EVEDA project

Knaster¹,

Garin

Matsumoto

et al. 2017

Nucl. Fusion

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IFMIF, the International Fusion Materials Irradiation Facility, is presently in its engineering validation and engineering design activities (EVEDA) phase under the Broader Approach Agreement. The engineering design activity (EDA) phase was successfully accomplished within the allocated time. The engineering validation activity (EVA) phase has focused on validating the Accelerator Facility (AF), the Target Facility and the Test Facility (TF) by constructing prototypes. The ELTL at JAEA, Oarai successfully demonstrated the long-term stability of a Li flow under the IFMIF’s nominal operational conditions keeping the specified free-surface fluctuations below ±1 mm in a continuous manner for 25 d. A full-scale prototype of the high flux test module (HFTM) was successfully tested in the HELOKA loop (KIT, Karlsruhe), where it was demonstrated that the irradiation temperature can be set individually and kept uniform. LIPAc, designed and constructed in European labs under the coordination of F4E, presently under installation and commissioning in the Rokkasho Fusion Institute, aims at validating the concept of IFMIF accelerators with a D+ beam of 125 mA continuous wave (CW) and 9 MeV. The commissioning phases of the H+/D+ beams at 100 keV are progressing and should be concluded in 2017; in turn, the commissioning of the 5 MeV beam is due to start during 2017. The D+ beam through the superconducting cavities is expected to be achieved within the Broader Approach Agreement time frame with the superconducting cryomodule being assembled in Rokkasho. The realisation of a fusion-relevant neutron source is a necessary step for the successful development of fusion. The ongoing success of the IFMIF/EVEDA involves ruling out concerns about potential technical showstoppers which were raised in the past. Thus, a situation has emerged where soon steps towards constructing a Li(d,xn) fusion-relevant neutron source could be taken, which is also justified in the light of costs which are marginal to those of a fusion plant.

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Section: Discussionmentioning

confidence: 99%

“…This opening is closed during irradiation periods by two concrete shielding plugs (SPs) 2.5 m high in total. The inner walls of the TC are covered by a closed steel liner [23].…”

Section: Edasmentioning

confidence: 99%

Section: The Test Facilitymentioning

confidence: 99%

Section: Feasibility Of Irradiating the Small Specimens Under A Unifo...mentioning

confidence: 99%

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Overview of the IFMIF/EVEDA project

Knaster¹,

Garin

Matsumoto

et al. 2017

Nucl. Fusion

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“…Against this background, Japan's fusion reactor development plans to acquire initial irradiation data using a fusion neutron source. Compared to the amount of neutrons generated by IFMIF conducted by IFMIF/EVEDA project [2][3][4][5][6][7][8][9][10][11][12][13][14][15][16], the amount of neutrons generated by the fusion neutron source in Japan will be half the amount of neutrons generated by IFMIF. By starting the irradiation test at an early stage, it will be possible to acquire the initial irradiation data by around 2035.…”

Section: Introductionmentioning

confidence: 95%

Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules

Sato¹,

Kasugai²,

Ochiai³

et al. 2021

Nucl. Fusion

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We have established a conceptual design of Advanced Fusion Neutron Source (A-FNS). In order to obtain irradiation data required in qualifying materials of fusion DEMO DT reactor, we newly designed nine test modules (TMs) to be implemented in the A-FNS. The design of the test modules is based on a new distinctive maintenance scheme: ‘horizontal maintenance method integrated with the shielding plug’. By integrating the TMs with the shield plug and transferring those from the test cell to the access cell, we can avoid disconnecting and connecting the huge amounts of the pipes and cables by means of the remote handling inside the test cell. We determined a configuration of the TMs in the test cell so as to achieve the required irradiation data for each of the test modules. The maximum dpa of F82H specimens in the TM for blanket structural material was about 10 dpa/fpy, which was designed to fulfil critical requirement by accumulated irradiation for two years and operation duration for four years with the operation availability of 50%. A-FNS was designed so that the huge amounts of neutrons generated can be utilized for various non-fusion purposes as well as the fusion materials irradiation. We newly designed a module to produce the significant amount of 99Mo for a medical purpose. The module for such a non-fusion purpose can be installed in the test cell with the compatibility of the fusion materials irradiation tests.

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