European DEMO divertor target: Operational requirements and material-design interface

You, J. H.; Visca, E.; Bachmann, C.; Barrett, T.; Crescenzi, F.; Fursdon, M.; Greuner, H.; Guilhem, D.; Languille, P.; Li, M.; McIntosh, S.; Müller, A. von; Reiser, J.; Richou, M.; Rieth, M.

doi:10.1016/j.nme.2016.02.005

Cited by 140 publications

(78 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In a fusion reactor, heat exhaust is one of the most challenging engineering issues, also due to the high heat flux (HHF) expected on the divertor targets. For DEMO, loads from 10 −2 , for quasi-stationary operation, to 17 − 21 −2 , when slow transient events occur, are predicted locally in the narrow region near the strike point [1]. Among the different layouts, the tungsten (W) monoblock design represents one of the most suitable technological solutions for plasma facing components, since it has already met the present ITER design requirements [2].…”

Section: Introductionmentioning

confidence: 99%

Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test

Dose

Roccella

Richou

et al. 2019

Fusion Engineering and Design

View full text Add to dashboard Cite

In this paper, a comparison is presented among the ultrasonic measures of different W-monoblock mock-ups following high heat flux tests. The DEMO reference solution for the divertor targets (ITER-like) is compared with two other concepts, in which the interlayer between monoblocks and tube has been engineered to increase the performance of the component (Thermal Break Interlayer, Thin Graded Interlayer). Ultrasonic measurements have been performed at the depths of interest. The reflected signal amplitude and time of flight at defined depths are used to determine the shape and entity of the defect, when present. For each concept, the most frequently observed defects due to thermal loading are then identified. Preliminary post-mortem analysis confirms the results from the ultrasonic tests, proving the defect imaging capability of such non-destructive technique for advanced W-monoblock concepts.

show abstract

Section: Introductionmentioning

confidence: 99%

Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test

Dose

Roccella

Richou

et al. 2019

Fusion Engineering and Design

View full text Add to dashboard Cite

show abstract

“…The main future plasma facing materials (PFMs) for next-generation fusion devices are tungsten (W) and tungsten-based alloys, because they combines a high melting point, low sputtering rate, low vapor pressure, and low tritium retention. Copper (Cu) and its alloys, especially CuCrZr [1], has been widely studied for its heat sink applications because of their high conductivity and high mechanical performance [2] [3]. Therefore, many design concepts for next-generation fusion devices include W based materials joined to a Cu or CuCrZr heat sink.…”

Section: Introductionmentioning

confidence: 99%

Evolution of mechanical performance with temperature of W/Cu and W/CuCrZr composites for fusion heat sink applications

Tejado

Müller

You

et al. 2018

Materials Science and Engineering: A

Self Cite

View full text Add to dashboard Cite

Power exhaust and materials lifetime have been identified as key challenges for nextgeneration fusion devices. A water-cooled monoblock divertor, consisting of tungsten as the plasma facing material and copper-based composites as the heat sink, has been proposed as the baseline material. However, there is a large mismatch in the coefficient of thermal expansion and the elastic modulus between these metals, which requires the development of new materials. The goal of this study is the mechanical and microstructural characterization of two composites materials, W-30 wt%Cu and W-30 wt%CuCrZr, produced using liquid infiltration in an open porous tungsten preform. To reproduce the most adverse in-service conditions, materials were characterized under high vacuum atmosphere up to 800 °C. From the measured mechanical properties, a remarkable temperature dependence can be assessed, since it is noticeable that for both materials, tensile and flexural strength equally decrease as the measurement temperature increases. However, the fracture behaviour of W-30CuCrZr is on average 25% higher than that of W-30Cu (21 MPa.m 1/2 versus 17 MPa.m 1/2 at RT) although this gap is narrower at higher temperatures; at 800 °C, the contribution of the Cu-based phase is quite low, thus fracture is primary controlled by the W initial skeleton. From these values, it can be inferred that the the yield strength and fracture toughness of W-30CuCrZr composite are superior, whilst it presented lower elastic modulus and rupture strain values than the W-30Cu composite. As a result, the metal matrix composites presented in this article could effectively dissipate heat while overcoming the thermal stresses produced during operation, since a decent thermomechanical performance was observed at relevant reactor temperatures. This is of vital importance to enhance the performance, life cycle, and reliability of the component.

show abstract

“…ENEA that is involved in the R&D activities of the Work Package 'Divertor' [1], designed and optimized the ITER-like target concept according to monoblock design (rectangular tungsten blocks as armor, with a pure cast of soft Cu interlayer that are joined onto an actively cooled substrate, the heat sink, made of precipitation hardened copper alloy CuCrZr). The outcomes of this design together with first manufactured trials and High Heat Flux tests (HHFTs) showed that the reduced W monoblok dimensions had a structural impact on the failure behavior of these components [2].…”

Section: Introductionmentioning

confidence: 99%

FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO

Crescenzi

Cacciotti

Cerri

et al. 2018

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

The divertor is one of the most challenging components for DEMO reactor both from the design and fabrication technology point of view, since it must be capable to withstand the high heat fluxes (HHF) expected during normal operation (up to 10 MW/m²) and slow transient events (up to 20 MW/m²), like loss of plasma detachment. Within the frame of the EUROfusion Consortium the "Target development" subproject inside the Work Package 'Divertor' (WPDIV) has been dedicated to achieve this performance studying different concepts.ENEA focused on the "ITER-like" target that consists of applying the ITER design and fabrication technology to DEMO targets. The ITER-like concept mock-up was at first designed and optimized by FE analysis then manufactured and checked by non-destructive testing (NDT), finally thermal fatigue testing (TFT) and destructive testing (DT) were performed too .This paper reports the comparison of the thermal behavior of the ITER-like mock-ups between the analysis performed using ANSYS-CFX (Computational Fluid Dynamic analysis, CFD) and the outcome of the High Heat Flux tests (HHF) made at GLADIS facility. Finally the mechanical behavior of the mock-ups has been compared in terms of ratchetting applying dedicated criteria of the ITER SDC-IC and the fatigue lifetime has been estimated by means of Low Cycle Fatigue Curves (LCFC).

show abstract

European DEMO divertor target: Operational requirements and material-design interface

Cited by 140 publications

References 8 publications

Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test

Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test

Evolution of mechanical performance with temperature of W/Cu and W/CuCrZr composites for fusion heat sink applications

FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO

Contact Info

Product

Resources

About