Characterization of CuCrZr and CuCrZr/SS joint strength for different blanket components manufacturing conditions

Gillia, O.; Briottet, Laurent; Chu, I.; Lemoine, P.; Rigal, Emmanuel; Peacock, Alan T.

doi:10.1016/j.jnucmat.2008.12.244

Cited by 11 publications

(5 citation statements)

References 7 publications

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“…Instead, there is scope for improved copper based mat erials which utilise strengthening mechanisms which are more resistant to irradiation such as Laves phases, bi-modal precipitate microstructures and metal matrix composites [331][332][333]. In considering such enhancements, care must be taken to consider the entire thermal history of the product when assessing material performance; the many complex cycles and operations to achieve full-scale jointed multi-material parts can result in significant deviation in microstructure and material properties between manufactured and implemented conditions, as encounter ed previously due to the non-equilibrium nature of traditional copper alloy strengthening mechanisms such as PH [334,335].…”

Section: Future Outlook and Opportunitiesmentioning

confidence: 99%

Baseline high heat flux and plasma facing materials for fusion

et al. 2017

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In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).

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Section: Future Outlook and Opportunitiesmentioning

confidence: 99%

Baseline high heat flux and plasma facing materials for fusion

et al. 2017

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“…Extensive studies on the mechanical properties of CuCrZr alloy have been conducted (DeGroh et al, 2008;Edwards et al, 2007;Nomura et al, 2002). Performances of the joints of CuCrZr alloy to other alloys have also been studied by various groups (Gillia et al, 2009;Sahlot et al, 2018;Wei et al, 2018).…”

Section: Introductionmentioning

confidence: 99%

Vacuum joints of CuCrZr alloy for high-heat-load photon absorber

Li¹,

Jin²,

Zhu³

et al. 2022

J Synchrotron Rad

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A photon absorber, as a critical component of a synchrotron front-end, is mainly used to handle high-heat-load synchrotron radiation. It is mostly made of dispersion strengthened copper or CuCrZr which can retain high performance at elevated temperatures. Joining processes for vacuum, including tungsten inert gas welding (TIG) and electron beam welding (EBW), are novel ways to make a long photon absorber from two short ones and reduce power density. The mechanical properties of TIG joints and EBW joints of CuCrZr to the same material are obtained by tensile tests at 20°C, 100°C, 200°C, 300°C and 400°C. Testing results indicate that the tensile strength and yield strength of both vacuum joints decline as temperature increases. Compared with TIG joints, EBW joints have higher strength, better ductility and a more stable performance. An engineering conservative acceptance criteria of the vacuum joints is created by the polynomial fitting method. A novel welded photon absorber with a total length of 600 mm has been successfully designed and manufactured. Finite-element analysis by ANSYS shows that the maximum temperature, equivalent stress and strain are only 31.5%, 36.2% and 1.3%, respectively, of the corresponding thresholds. The welded photon absorbers with EBW joints will be applicable in the highest-heat-load front-end in the Shanghai Synchrotron Radiation Facility Phase-II beamline project.

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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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Characterization of CuCrZr and CuCrZr/SS joint strength for different blanket components manufacturing conditions

Cited by 11 publications

References 7 publications

Baseline high heat flux and plasma facing materials for fusion

Baseline high heat flux and plasma facing materials for fusion

Vacuum joints of CuCrZr alloy for high-heat-load photon absorber

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

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