Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

Bargalló, Enric; Alguacil, Natalia; Abal, Javier; Dies, J.; Blas, A. de; Tapia, Carlos; Moya, Joaquin; Ibarra, Á.

doi:10.1016/j.fusengdes.2015.06.011

Cited by 6 publications

(1 citation statement)

References 5 publications

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“…However, for the case of the AF, the operation will be more discontinuous due to the unavoidable trips and short stops of this kind of facility, therefore specific approaches to estimate the influence of such operation patterns on availability were needed. The RAMI database has been generated for the analysis mainly through the collection of reliability data from related field facilities [60,108,109] (accelerator facilities, fusion, fission fields, generic databases, etc), and also through estimations of Taking into account the scheduled maintenance time, the operational availability requirement of 70% over the calendar year is translated into the inherent availability requirement of 75% over the 11 months of scheduled operation time. This inherent availability requirement, allocated among the facilities, can be seen in table 4.…”

Section: The Availability Of Ifmif: Rami and Maintenance Studiesmentioning

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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Section: The Availability Of Ifmif: Rami and Maintenance Studiesmentioning

confidence: 99%