IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li(d,xn) neutron source: Current status and future options

Knaster, J.; Arbeiter, Frederik; Cara, Philippe; Chel, S.; Facco, A.; Heidinger, R.; Ibarra, Á.; Kasugai, Atsushi; Kondo, Hiroo; Miccichè, G.; Ochiai, Kentaro; O’hira, Shigeru; Okumura, Y.; Sakamoto, K.; Wakai, Eiichi

doi:10.1016/j.nme.2016.04.012

Cited by 49 publications

(23 citation statements)

References 46 publications

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“…The results of the measurements in the ELTL are not yet published by the time of publication of this paper [31], but given the optimal experimental setup, a close result with the calculations here included is expected, thus providing soundness to this estimation for IFMIF [6, 7]. …”

Section: Resultsmentioning

confidence: 74%

“…1), the International Fusion Materials Irradiation Facility, is presently under its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Japan and EURATOM. IFMIF/EVEDA entered into force on June 2007 with the mandate to produce an integrated engineering design of IFMIF and the data necessary for future decisions on the construction, operation, exploitation and decommissioning of IFMIF, and to validate continuous and stable operation of each IFMIF sub-system [6].…”

Section: Introductionmentioning

confidence: 99%

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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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Section: Resultsmentioning

confidence: 74%

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 multiple loads that are inherent in fusion require complex testing facilities. It will not be possible to test large-scale components under nuclear irradiation without building a machine akin to a demonstrator, so it is most probable that the effect of irradiation will have to be included from irradiation of materials in facilities such as IFMIF [23] and the smaller DONES [24] from a combination of fission reactors and spallation sources, although this is less than ideal. Physical testing is time-consuming and expensive-the first wall panels for ITER have been under development for a decade or more and are still only at one-third or one-half scale despite the existence of multiple test facilities.…”

Section: Accelerating Demonstrator Developmentmentioning

confidence: 99%

Engineering challenges for accelerated fusion demonstrators

Surrey

2019

Phil. Trans. R. Soc. A.

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There are several programmes within the fusion community that are engaged in the design of fusion devices to follow the International Thermonuclear Experimental Reactor (ITER), referred to as ‘demonstrators’. These programmes have identified many issues over the past decade, and research now concentrates on optimizing the combination of systems against a set of Key Performance Indicators (KPI) which may vary between programmes. While the return on investment in and experience from ITER is seen as an important factor in this research there are significant differences in the operational conditions and KPI of demonstrators that generate additional problems requiring different solutions. Among these problems are the necessary use of uncommon materials for structural and functional purposes, the impact of the availability KPI on basic machine design, configuration and component lifetime and the integration of the tritium fuel and thermodynamic cycles. These raise issues of component manufacture and standards and of resource availability in the required quantities and quality that are independent of device size and design. Interpreting ‘accelerating fusion’ in a wider sense, the impact of these issues, analysed in respect of developmental timescales, shows that a strategy of early engagement with the industrial supply chain and the development of computational engineering testing and verification will be essential to prevent prolonged timescales to fusion progress. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’

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“…A materials test facility to test and validate materials for DEMO under a fusion relevant neutron load and spectrum. The International Fusion Materials Irradiation Facility (IFMIF) [11] is an accelerator-based neutron source. The materials test facility should operate in parallel to ITER such that the new materials are validated before DEMO is going to be built.…”

Section: The European Roadmap To Fusion Energymentioning

confidence: 99%

Scientific and technical challenges on the road towards fusion electricity

Donné¹,

Federici²,

Litaudon³

et al. 2017

J. Inst.

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A: The goal of the European Fusion Roadmap is to deliver fusion electricity to the grid early in the second half of this century. It breaks the quest for fusion energy into eight missions, and for each of them it describes a research and development programme to address all the open technical gaps in physics and technology and estimates the required resources. It points out the needs to intensify industrial involvement and to seek all opportunities for collaboration outside Europe. The roadmap covers three periods: the short term, which runs parallel to the European Research Framework Programme Horizon 2020, the medium term and the long term.ITER is the key facility of the roadmap as it is expected to achieve most of the important milestones on the path to fusion power. Thus, the vast majority of present resources are dedicated to ITER and its accompanying experiments. The medium term is focussed on taking ITER into operation and bringing it to full power, as well as on preparing the construction of a demonstration power plant DEMO, which will for the first time demonstrate fusion electricity to the grid around the middle of this century. Building and operating DEMO is the subject of the last roadmap phase: the long term. Clearly, the Fusion Roadmap is tightly connected to the ITER schedule. Three key milestones are the first operation of ITER, the start of the DT operation in ITER and reaching the full performance at which the thermal fusion power is 10 times the power put in to the plasma. The Engineering Design Activity of DEMO needs to start a few years after the first ITER plasma, while the start of the construction phase will be a few years after ITER reaches full performance. In this way ITER can give viable input to the design and development of DEMO. Because the neutron fluence in DEMO will be much higher than in ITER, it is important to develop and validate materials that can handle these very high neutron loads. For the testing of the materials, a dedicated 14 MeV neutron source is needed. This DEMO Oriented Neutron Source (DONES) is therefore an important facility to support the fusion roadmap. K: Nuclear instruments and methods for hot plasma diagnostics; Instrumentation for neutron sources

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IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li(d,xn) neutron source: Current status and future options

Cited by 49 publications

References 46 publications

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

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

Engineering challenges for accelerated fusion demonstrators

Scientific and technical challenges on the road towards fusion electricity

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