RAMI analysis for ITER fuel cycle system

Okayama, K.; Houtte, D. van; Sagot, F.; Maruyama, S.

doi:10.1016/j.fusengdes.2011.01.121

Cited by 16 publications

(3 citation statements)

References 5 publications

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“…The RAMI analysis for the ITER fuel cycle system [8] identified several failure modes with high risks, majority of which were removed by implementing risk reducing means. However, some most critical risks remain, e. g. se veral critical components of the tritium plant, which are not easily replaced or repaired.…”

Section: Iter Rami Approachmentioning

confidence: 99%

Application of probabilistic safety and reliability analysis for a system of fusion facility

Voronov¹,

Alzbutas²

2014

Energetika

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Fusion or thermonuclear power is a promising, literally endless source of energy. Development of fusion power is still in investigation and experimentation phases and a number of fusion facilities are under construction in Europe. Since fusion energy is innovative and fusion facilities contain unique and expensive equipment an issue of their reliability is very important from their efficiency perspective.A Reliability, Availability, Maintainability, Inspectability (RAMI) Analysis is being performed or is going to be performed in the nearest future for such fusion facili ties as ITER and DEMO in order to ensure reliable and efficient operation for experi ments (e. g. in ITER) or for energy production purposes (e. g. in DEMO). On the other hand, rich experience of the Reliability and Probabilistic Safety Analysis (PSA) exists in nuclear industry for fission power plants and other nuclear installations.In this article, the Wendelstein 7-X (W7-X) facility is mainly considered. It is a stel larator type fusion facility under construction in the Max-Planck-Institut für Plasmaphysik, Greifswald, Germany (IPP). In the frame of cooperation between the IPP and the Lithuanian Energy Institute (LEI) under the European Fusion Development Agreement a pilot project of a reliability analysis of the W7-X systems was performed with a purpose to adopt NPP PSA experience for fusion facility systems. During the project a reliability analysis of a divertor target cooling circuit, which is an important system for permanent and reliable operation of in-vessel components of the W7-X, was performed.

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Section: Iter Rami Approachmentioning

confidence: 99%

Application of probabilistic safety and reliability analysis for a system of fusion facility

Voronov¹,

Alzbutas²

2014

Energetika

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“…H phase [4]. This value leads to drastically decrease the inherent availability of the overall machine operation from 60% in H phase down to 51.8% in D-T phase.…”

Section: Functional Analysismentioning

confidence: 99%

ITER operational availability and fluence objectives

Houtte¹,

Okayama²,

Sagot³

2011

Fusion Engineering and Design

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“…Therefore, the PSA methodology for fusion reactors has not been established. RAMI analysis has been performed for some relevant systems of fusion reactors, such as RAMI analysis for ITER fuel cycle system [4], RAMI analysis for ITER Control Data Access and Communication (CODAC) functions [5] and RAMI analysis for DEMO HCPB blanket concept cooling system [6]. Bargallo E performed RAMI analyses for the IFMIF accelerator facility and first availability allocation between systems [7].…”

Section: Introductionmentioning

confidence: 99%

A New Reliability Allocation Method Based on PSA and AHP for Fusion Reactors

Sun

et al. 2022

Energies

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Reasonable and feasible reliability index allocation is significant for improving safety and reducing costs for fusion reactors. Although the reliability index is allocated when designing some key systems, reliability allocation is not implemented from the overall layer to the system and component layers for fusion reactors. In this contribution, fusion reactors are divided into different layers by applying the Analytic Hierarchy Process (AHP); these layers include the overall layer, system layer and component layer, failure mode layer, etc. Combining the Probabilistic Safety Assessment (PSA) model for fusion reactors and AHP, the reliability index is allocated from the overall layer to the system and component layer. Firstly, a new reliability index allocation method based on PSA and AHP for fusion reactors is proposed. Secondly, the PSA model for an in-vessel LOCA accident of fusion reactors is selected as a case study to demonstrate the applications of the proposed method. Lastly, the relationship between PSA, items safety classification and reliability allocation are discussed. The allocation results indicate that the proposed method provides a more systematic reliability allocation scheme and contributes to improving the safety and economy of fusion reactors.

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RAMI analysis for ITER fuel cycle system

Cited by 16 publications

References 5 publications

Application of probabilistic safety and reliability analysis for a system of fusion facility

Application of probabilistic safety and reliability analysis for a system of fusion facility

ITER operational availability and fluence objectives

A New Reliability Allocation Method Based on PSA and AHP for Fusion Reactors

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