A Stepped Approach from IFMIF/EVEDA Toward IFMIF

Ibarra, Á.; Heidinger, R.; Barabaschi, P.; Mota, F.; Mosnier, A.; Cara, Philippe; Nitti, Francesco

doi:10.13182/fst13-778

Cited by 63 publications

(28 citation statements)

References 16 publications

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“…Conclusive thermohydraulic analysis of the lithium flow of a Li(d,xn) neutron source with one only 125 mA CW 40 MeV deuteron accelerator and a beam footprint of 200 × 50 mm 2 colliding on a 15 m/s flowing lithium at 523 K, as DONES [51] or A-FSN [52] could exhibit, is presently missing. It is obvious that the halved beam power will lead to <574 K than those that IFMIF will reach in its free surface (see Fig.…”

Section: Resultsmentioning

confidence: 99%

“…The lower it is, the lower the corresponding vapour pressure and thus reduced vaporization rate. Therefore, the value of 76.7 g of total vaporized lithium per year of operation of IFMIF, assuming the 70% target specified facility availability, is a conservative value usable for a future simplified Li(d,xn) fusion relevant neutron source with one only deuteron accelerator line [51, 52]. …”

Section: Resultsmentioning

confidence: 99%

“…In the case that a simplified version of IFMIF is constructed with one only deuteron accelerator 125 mA CW at 40 MeV [51, 52], the maximum annual vaporization will always be smaller than the 76.7 g here reported.…”

Section: Discussionmentioning

confidence: 97%

See 2 more Smart Citations

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: 99%

Section: Resultsmentioning

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 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%

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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The IFMIF-DONES Project: Design Status and Main Achievements Within the EUROfusion FP8 Work Programme

Bernardi

Ibarra²,

Arbeiter

et al. 2022

J Fusion Energ

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International Fusion Materials Irradiation Facility-DEMO-Oriented NEutron Source (IFMIF-DONES) is a high-intensity neutron irradiation facility for qualification of fusion reactor materials, which is being designed as part of the European roadmap to fusion-generated electricity. Its main purpose is to study the behavior of materials properties under irradiation in a neutron flux able to simulate the same effects in terms of relevant nuclear responses as those expected in the first wall of the DEMO reactor which is envisaged to follow ITER. It is thus a key facility to support the design, licensing and safe operation of DEMO as well as of the fusion power plants that will be developed afterwards. The start of its construction is foreseen in the next few years. In this contribution, an overview of the IFMIF-DONES neutron source is presented together with a snapshot of the current engineering design status and of the relevant key results achieved within the EUROfusion Work Package Early Neutron Source (WPENS) as part of the 2014–2020 EURATOM Research and Training Programme, complementary to the EU Horizon 2020 Framework Programme (FP8). Moreover, some information on the future developments of the project are given.

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A Stepped Approach from IFMIF/EVEDA Toward IFMIF

Cited by 63 publications

References 16 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

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

The IFMIF-DONES Project: Design Status and Main Achievements Within the EUROfusion FP8 Work Programme

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