IFMIF: overview of the validation activities

Knaster, J.; Arbeiter, Frederik; Cara, Philippe; Favuzza, P.; Furukawa, Tomohiro; Groeschel, F.; Heidinger, R.; Ibarra, Á.; Matsumoto, Hiroshi; Mosnier, A.; Serizawa, Hisashi; Sugimoto, M.; Suzuki, Hisashi; Wakai, Eiichi

doi:10.1088/0029-5515/53/11/116001

Cited by 69 publications

(40 citation statements)

References 28 publications

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“…Prototype elements for IFMIF are in construction and under test in Japan, Italy and Germany [13,14]. 5.…”

Section: Advantages Of Fusion Powermentioning

confidence: 99%

Nuclear fusion and its large potential for the future world energy supply

Ongena

2016

Nukleonika

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Abstract. An overview of the energy problem in the world is presented. The colossal task of 'decarbonizing' the current energy system, with ~85% of the primary energy produced from fossil sources is discussed. There are at the moment only two options that can contribute to a solution: renewable energy (sun, wind, hydro, etc.) or nuclear fi ssion. Their contributions, ~2% for sun and wind, ~6% for hydro and ~5% for fi ssion, will need to be enormously increased in a relatively short time, to meet the targets set by policy makers. The possible role and large potential for fusion to contribute to a solution in the future as a safe, nearly inexhaustible and environmentally compatible energy source is discussed. The principles of magnetic and inertial confi nement are outlined, and the two main options for magnetic confi nement, tokamak and stellarator, are explained. The status of magnetic fusion is summarized and the next steps in fusion research, ITER and DEMO, briefl y presented.

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“…Prototype elements for IFMIF are in construction and under test in Japan, Italy and Germany [13,14]. 5.…”

Section: Advantages Of Fusion Powermentioning

confidence: 99%

Nuclear fusion and its large potential for the future world energy supply

Ongena

2016

Nukleonika

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“…In parallel, for validating the developed design features, prototyping sub-projects were carried out which consist of the design, manufacturing, and testing of the following prototypical systems [14,15]:…”

Section: Introductionmentioning

confidence: 99%

The IFMIF-DONES project: preliminary engineering design

Ibarra

Arbeiter²,

Bernardi

et al. 2018

Nucl. Fusion

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The need of a neutron source for the qualification of materials to be used in future fusion power reactors has been recognized in the European Union (EU) fusion programme for many years. The construction and exploitation of this facility is presently considered to be critical to the construction of the DEMOnstration Power Plant (DEMO). This issue has prompted the EU to launch activities for the design and engineering of the International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source (IFMIF-DONES) facility based on and taking profit of the results obtained in the Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) project, presently conducted in the framework of the EU–Japan Bilateral Agreement on the Broader Approach to Fusion. These activities and research and development work for the IFMIF-DONES plant are presently taking place in the framework of a work package of the EUROfusion Consortium, in direct collaboration with the Fusion for Energy organization. The main objective of these activities is to consolidate the design and underlying technology basis in order to be ready for the start of the IFMIF-DONES construction as early as possible. In this paper, an overview and the present status of the IFMIF-DONES engineering design is presented for a generic site, making emphasis on the recent design evolution from previous phases.

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“…The BA activities comprise the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) [3,4], the International Fusion Energy Research Center (IFERC) [5], and the Satellite Tokamak [6] started from 2007 in the joint program. The main function of the IFMIF is to generate the intense fusion neutrons by injecting the deuteron beams accelerated to high energy onto the liquid lithium flow at 250…”

Section: Introductionmentioning

confidence: 99%

Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

Wakai

Watanabe

Ito

et al. 2016

Plasma and Fusion Research

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The lithium target facility of IFMIF (International Fusion Materials Irradiation Facility) consists of target assembly, lithium main loop, lithium purification loops, the diagnostic systems, and remote handling system. Major impurities in the lithium loop are proton, deuterium, tritium, 7-Be, activated corrosion products and the other species (C, N, O). It is very important to remove nitrogen content in lithium loop during operation, in order to avoid the corrosion/erosion of the nozzle of lithium target for the stable lithium flow on the target assembly. Nitrogen in the lithium can be removed by N hot trap using Fe-5%Ti alloy at temperatures from 400 to 600• C. In this study, the specification and the detailed design were evaluated, and the component of N hot trap system was fabricated.

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IFMIF: overview of the validation activities

Cited by 69 publications

References 28 publications

Nuclear fusion and its large potential for the future world energy supply

Nuclear fusion and its large potential for the future world energy supply

The IFMIF-DONES project: preliminary engineering design

Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

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