EU contribution to the procurement of blanket first wall and divertor components for ITER

Lorenzetto, P.; Andrade, José Henrique de; Banetta, Stefano; Cicero, Tindaro; Dellopoulos, Georges; Durocher, A.; Escourbiac, F.; Felip, Montse; Ferrand, L.; Gavila, P.; Gicquel, S.; Guerrini, L.; Heikkinen, S.; Marshall, Paul; Merola, M.; Mitteau, R.; Raffray, R.; Riccardi, B.

doi:10.1016/j.fusengdes.2018.04.050

Cited by 7 publications

(4 citation statements)

References 11 publications

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“…In total 420 mg of tritium has been introduced (5 mg -PTE, 35 mg -DTE1 and 380 mg -TTE) [19]. Tritium can be produced in vacuum vessel also as a product of the D -D fusion reaction (4).…”

Section: Methodsmentioning

confidence: 99%

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Novel method for determination of tritium depth profiles in metallic samples

et al. 2019

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Novel method for determining the depth profile of tritium in metallic samples has been demonstrated. Tritium accumulation in the fusion reactor materials is considered as a radiological issue due to its radioactivity. Therefore, tritium behavior prediction and estimation of its overall retention in fusion devices is of high importance. Proposed method in this study allows to measure depth profile of tritium in the metallic samples after exposure to tritium containing plasma, tritium gas or after irradiation with neutrons resulting in the tritium formation. In the method, successive layers of metal are removed using appropriate etching agent in the controlled regime and amount of evolved gases measured by the means of chromatography (gas composition and release rate) and proportional gas flow detector (tritium). Results on tritium profile in neutron irradiated, plasma exposed and tritium gas loaded beryllium have been reported and possible applications of the method for other metallic samples have been tested within this research.

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“…In total 420 mg of tritium has been introduced (5 mg -PTE, 35 mg -DTE1 and 380 mg -TTE) [19]. Tritium can be produced in vacuum vessel also as a product of the D -D fusion reaction (4).…”

Section: Methodsmentioning

confidence: 99%

“…The first wall of the Blanket will be covered with metallic beryllium. Divertorthe component that will be withstanding the highest surface heat loads of the ITER machine will be made of metallic tungsten [4].…”

Section: Introductionmentioning

confidence: 99%

Novel method for determination of tritium depth profiles in metallic samples

et al. 2019

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“…An example that imposes all of these conditions is in the plasma facing components (PFC) of the International Thermonuclear Experimental Reactor (ITER) [85,86]. In the PFC, brazed joints can be found in the first wall, limiter, baffle, and divertor components [87,88]. There are different armor material candidates for the PFC, including beryllium and tungsten (in both cases to be joined with Cu alloy heat sink materials) [86,89,90].…”

Section: Fillers For Extreme Environmentsmentioning

confidence: 99%

High Entropy Alloys as Filler Metals for Joining

Luo

Xiao

Hardwick

et al. 2021

Entropy

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In the search for applications for alloys developed under the philosophy of the High Entropy Alloy (HEA)-type materials, the focus may be placed on applications where current alloys also use multiple components, albeit at lower levels than those found in HEAs. One such area, where alloys with complex compositions are already found, is in filler metals used for joining. In soldering (<450 °C) and brazing (>450 °C), filler metal alloys are taken above their liquidus temperature and used to form a metallic bond between two components, which remain both unmelted and largely unchanged throughout the process. These joining methods are widely used in applications from electronics to aerospace and energy, and filler metals are highly diverse, to allow compatibility with a broad range of base materials (including the capability to join ceramics to metals) and a large range of processing temperatures. Here, we review recent developments in filler metals relevant to High Entropy materials, and argue that such alloys merit further exploration to help overcome a number of current challenges that need to be solved for filler metal-based joining methods.

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“…These are the most critical phases of the manufacturing route because of their influence on the final distortion and residual stresses accumulated by the component. Several works have been carried out on this issue, specially about the influence over the CuCrZr properties [13] [16] [4].…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis of the manufacturing processes of a mock-up of the ITER NHF First Wall Panel

González

Chiumenti

Cervera

et al. 2018

Fusion Engineering and Design

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The objective of ITER is to build a new Tokamak, with the goal of demonstrating the scientific and technical feasibility of fusion power. The First Wall Panels are the inner component of the reactor, built with different materials that must support high heat flux levels inside the vacuum vessel. The manufacturing processes of the First Wall are a complex procedure including bending, hipping and cutting procedures which, in general, lead to residual stresses and distortions of the fabricated component. In this work, the analysis of the thermo-mechanical response of a simplified prototype of the ITER NHF First Wall Panel is presented from the numerical point of view. The experimental procedure within each phase of the whole manufacturing process is described. Residual stresses and distortions have been measured and analyzed. The numerical simulation of the manufacturing process includes the description of the main hypothesis, the applied loads and the boundary conditions assumed at every stage of the process. Special attention is paid to the simulation of machining and cutting by means of an adhoc element deactivation strategy. The numerical results are compared with the experimental evidence to show the prediction capability and the limitations of the proposed numerical model.

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EU contribution to the procurement of blanket first wall and divertor components for ITER

Cited by 7 publications

References 11 publications

Novel method for determination of tritium depth profiles in metallic samples

Novel method for determination of tritium depth profiles in metallic samples

High Entropy Alloys as Filler Metals for Joining

Numerical analysis of the manufacturing processes of a mock-up of the ITER NHF First Wall Panel

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