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

Knaster, J.; Ibarra, Á.; Abal, Javier; Abou-Sena, Ali; Arbeiter, Frederik; Arranz, F.; Alguacil, Natalia; Bargalló, Enric; Beauvais, Pierre-Yves; Bernardi, D.; Casal, N.; Carmona, J. M.; Chauvin, Nicolas; Comunian, M.; Delferrière, O.; Delgado, Antonio; Diaz-Arocas, P.; Fischer, U.; Frisoni, M.; García, A. R.; Garin, P.; Gobin, R.; Gouat, P.; Groeschel, F.; Heidinger, R.; Ida, Masato; Kondo, Keitaro; Kikuchi, Takayuki; Kubo, T.; Tonqueze, Y. Le; Leysen, W.; Mas, Alicia; Massaut, V.; Matsumoto, Hiroshi; Miccichè, G.; Mittwollen, Martin; Mora, Juan C.; Mota, F.; Nghiem, P.; Nitti, Francesco; Nishiyama, Koichi; Ogando, F.; O’hira, Shigeru; Oliver, C.; Orsini, F.; Pérez, Daniel Milian; Pérez, Mario; Pinna, T.; Pisent, A.; Podadera, I.; Porfiri, M.; Pruneri, Giuseppe; Queral, V.; Rapisarda, D.; Román, Rodrigo Máximo Sánchez; Shingala, M.; Soldaini, M.; Sugimoto, M.; Theile, J.; Tian, Kuo; Umeno, H.; Uriot, D.; Wakai, Eiichi; Watanabe, Kazuyoshi; Weber, M.; Yamamoto, M.; Yokomine, Takehiko

doi:10.1088/0029-5515/55/8/086003

Cited by 67 publications

(41 citation statements)

References 82 publications

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“…The validation of the 50-65 dpa goals and the development of an engineering design database for FNSF are entirely dependent on the timely deployment of fusion relevant neutron facilities, such as IFMIF [13] and DONES [14]. However, the FNSF itself will provide the only opportunity to extend the understanding of materials behavior in the integrated multi-effects fusion environment, combining the fusion neutron spectrum, temperature and magnetic field gradients, cyclic operation, etc.…”

Section: Mtm and Main Attributesmentioning

confidence: 99%

“…The most important attributes for the MTM would be the fusion-relevant He/dpa ratio (10) and the much larger specimen volumes (up to 20 cm × 50 cm × 80 cm, mimicking the actual shape and volume of structural components)-much larger than the 10-500 mL specimens of currently proposed 14 MeV neutron sources. After irradiation, the tested materials could be contrasted with those of the International Fusion Materials Irradiation Facility (IFMIF) [13], the European DEMO-Oriented Neutron Source (DONES) [14], or other accelerator-based neutron environments, as discussed in Section 2. More advanced versions of the dual-cooled PbLi (DCLL) blanket along with ceramic breeder blankets could be tested in dedicated test blanket modules (TBM), as discussed in Section 3.…”

Section: Introductionmentioning

confidence: 99%

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TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

et al. 2016

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Abstract:The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. The most important attributes for MTM are the relevant He/dpa ratio (10-15) and the much larger specimen volumes compared to the 10-500 mL range available in the International Fusion Materials Irradiation Facility (IFMIF) and European DEMO-Oriented Neutron Source (DONES).

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Section: Mtm and Main Attributesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

et al. 2016

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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 successful accomplishment of the Engineering Design Activities (EDA) phase [7], together with the on-going success of the Engineering Validation Activities (EVA) phase [8, 9, 10], where only remains the accelerator facility to be validated, whose installation and commissioning in Rokkasho is advancing [11], has allowed to taking decisions on the construction of a fusion relevant neutron source. A facility capable to provide 14 MeV neutrons and the needed flux will be likely available by the middle of next decade, to timely characterize materials in compliance with fusion roadmaps.…”

Section: Introductionmentioning

confidence: 99%

“…The design of the Target Facility of IFMIF has already been described [7, 21]. Its layout, integrated in full IFMIF plant is visible in Fig.…”

Section: Introductionmentioning

confidence: 99%

An assessment of the evaporation and condensation phenomena of lithium during the operation of a Li(d,xn) fusion relevant neutron source

Knaster

Kanemura

Kondo

2016

Heliyon

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The flowing lithium target of a Li(d,xn) fusion relevant neutron source must evacuate the deuteron beam power and generate in a stable manner a flux of neutrons with a broad peak at 14 MeV capable to cause similar phenomena as would undergo the structural materials of plasma facing components of a DEMO like reactors. Whereas the physics of the beam-target interaction are understood and the stability of the lithium screen flowing at the nominal conditions of IFMIF (25 mm thick screen with +/–1 mm surface amplitudes flowing at 15 m/s and 523 K) has been demonstrated, a conclusive assessment of the evaporation and condensation of lithium during operation was missing. First attempts to determine evaporation rates started by Hertz in 1882 and have since been subject of continuous efforts driven by its practical importance; however intense surface evaporation is essentially a non-equilibrium process with its inherent theoretical difficulties. Hertz-Knudsen-Langmuir (HKL) equation with Schrage’s ‘accommodation factor’ η = 1.66 provide excellent agreement with experiments for weak evaporation under certain conditions, which are present during a Li(d,xn) facility operation. An assessment of the impact under the known operational conditions for IFMIF (574 K and 10−3Pa on the free surface), with the sticking probability of 1 inherent to a hot lithium gas contained in room temperature steel walls, is carried out. An explanation of the main physical concepts to adequately place needed assumptions is included.

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

Cited by 67 publications

References 82 publications

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

The IFMIF-DONES project: preliminary engineering design

An assessment of the evaporation and condensation phenomena of lithium during the operation of a Li(d,xn) fusion relevant neutron source

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