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UKAEA-CCFE-CP(20)752018
Within the DEMO first wall 3-D shape design activity the first study of the effect of misalignment has started. Such assessments have been conducted in the past for ITER and penalty factor maps have been created; this route could be a feasible approach in the case of DEMO wall design also. This paper details the first set of computational tests tha…
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UKAEA-CCFE-PR(20)642018
The JET outboard divertor targets are the in-vessel components which receive the largest heat flux density. Surface delamination, radial cracks, and tie rod failures have been observed in the outboard tungsten-coated CFC tiles, while bulk tungsten special lamellas were intentionally melted in dedicated experiments. These different types of damag…
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UKAEA-CCFE-CP(19)502019
Within the framework of EUROfusion DEMO First Wall and limiter design activities, the protection of the First Wall against power deposition peaks is being considered. During steady-state operation, the radiative power from the plasma could be considered uniformly spread on plasma-facing components. However, the presence of openings (i.e. g…
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UKAEA-CCFE-CP(19)062019
The next D-T campaign will push JET ITER-like Wall (IWL) to high divertor power and energy levels. During the 2016 campaign, the Strike Point (SP) sweeping permitted relevant H-mode scenarios without exceeding the temperature limits imposed by JET Operation Instructions (JOIs). In the subsequent shutdown, six outer divertor tungsten-coated 2D carbo…
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UKAEA-CCFE-PR(19)452019
The DEMO blanket attachment concept is challenging due to several factors: the harsh radiation environment, the thermal expansion, the electro-magnetic loads, the remote maintenance feasibility, and the accurate control of the alignment of the breeding blanket first wall during operation. There are two inboard and three outboard blanket segments…
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CCFE-PR(16)592016
The detachment of a beryllium tile from the ITER Normal Heat Flux (NHF) First Wall (FW) panels would result in an unacceptable degradation of panel performance. Such detachment has previously been observed under High Heat flux (HHF) testing of NHF FW prototypes, with initiation of de-bonding at tile edges and subsequent delamination occurring betwe…
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CCFE-PR(16)602016
The European ITER First Wall panel design relies on a HIP based manufacturing sequence. However, failures of the bond to the beryllium tile might occur during the fabrication and under high heat flux qualification. A dedicated project has been stablished between UKAEA/CCFE and F4E aiming to identify suitable repair techniques. One of the most prom…
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CCFE-PR(17)302015
The traditional method for static strength assessment of structures uses elastic stresses computed along critical ligaments and then divided into categories depending on their nature e.g. bending/membrane and primary/secondary. More recently, highly realistic plastic simulations are possible using FE (finite elements) which offer useful advantages …
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CCFE-PR(17)312015
The blanket attachment has to cope with gravity, thermal and electromagnetic loads, also it has to be installed and serviced by remote handling. Pre-stressed components suffer from stress relaxation in irradiated environments such as DEMO. To circumvent this problem pre-stressed component should be either avoided or shielded, and where possible key…
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2015
The traditional method for static strength assessment of structures uses elastic stresses computed along critical ligaments and then divided into categories depending on their nature e.g. bending/membrane and primary/secondary. More recently, highly realistic plastic simulations are possible using FE (finite elements) which offer useful advantages …
Showing 11 - 20 of 20 UKAEA Paper Results