Overview of progress on the European DEMO remote maintenance strategy

Crofts, Oliver; Loving, A.; Iglesias, Daniel; Coleman, M.; Siuko, Mikko; Mittwollen, Martin; Queral, V.; Vale, Alberto; Villedieu, E.

doi:10.1016/j.fusengdes.2015.12.013

Cited by 36 publications

(11 citation statements)

References 6 publications

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“…The SIFT features are associated to the nearest pixel using the coordinates of each feature. Then, the 3D points are obtained with (1). Hence, the SIFT matches can be used to associate two points in the 3D space rather than two points in the image.…”

Section: Epj Web Of Conferencesmentioning

confidence: 99%

“…The normal functioning of these reactors or unforeseen problems will lead to planned and unplanned shutdowns. During this period, Remote Handling Systems (RMS) will proceed with maintenance operations [1]. The RHS require special design for regular operations of inspection and maintenance in hard conditions, such as the high levels of radiation, temperature and residual magnetic fields.…”

Section: Introductionmentioning

confidence: 99%

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Remote inspection with multi-copters, radiological sensors and SLAM techniques

et al. 2018

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Abstract-Activated material can be found in different scenarios, such as in nuclear reactor facilities or medical facilities (e.g. in positron emission tomography commonly known as PET scanning). In addition, there are unexpected scenarios resulting from possible accidents, or where dangerous material is hidden for terrorism attacks using nuclear weapons. Thus, a technological solution is important to cope with fast and reliable remote inspection. The multi-copter is a common type of Unmanned Aerial Vehicle (UAV) that provides the ability to perform a first radiological inspection in the described scenarios. The paper proposes a solution with a multi-copter equipped with on-board sensors to perform a 3D reconstruction and a radiological mapping of the scenario. A depth camera and a Geiger-Müler counter are the used sensors. The inspection is performed in two steps: i) a 3D reconstruction of the environment and ii) radiation activity inference to localise and quantify sources of radiation. Experimental results were achieved with real 3D data and simulated radiation activity. Experimental tests with real sources of radiation are planned in the next iteration of the work.

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Section: Epj Web Of Conferencesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Remote inspection with multi-copters, radiological sensors and SLAM techniques

et al. 2018

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“…As well as a PF coilset allowing remote handling access, the divertor cassette must also be of handleable size and weight. The cutting and reconnection of services to in-vessel components is a major RH overhead [10] and designs which lengthen or complicate this process are not preferred. This counts most strongly against in-vessel coils of any design which may require many services and connections per port.…”

Section: Remote Handling (Rh)mentioning

confidence: 99%

Exploring a broad spectrum of design options for DEMO

Kemp

Wenninger²,

Federici³

et al. 2018

Fusion Engineering and Design

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In the pursuit of realistically achievable design options for demonstrating fusion electricity generation and tritium self-sufficiency in a device to follow ITER, it is vital to explore as fully as possible the available design space and technology options which might lead to a fusion power plant within the timescales envisioned by the EU Roadmap to Fusion Energy. The usual tool for exploring this space is a systems code, such as PROCESS, which seeks to model all important plant systems and physics to provide an integrated power plant design point. However, currently many of these models are tied to assumptions of ITER-like technology and therefore tend to lead to ITER-like plant solutions. This contribution describes a broader set of plant configurations being considered alongside the main baseline design, investigating the impacts on design and costs of designing for (1) flexi-pulsed-steady-state operation, (2) double-null divertors, and (3) the use of high-temperature superconductors. The focus of the work presented here, however, is on (4) advanced magnetic configurations such as snowflake and super-X divertors. We discuss the modifications necessary for the systems code to simulate these configurations and their performance, particularly the divertor geometry and power handling capability; rapid engineering analysis of TF and PF coil positions which can achieve both the required equilibrium and remote-handling access; and initial wider analysis of the physics, neutronics, and other considerations. The reductions in wall area available for breeding tritium affect the choice of blanket technology, and remote handling considerations have a strong impact on the configurations which can be considered reasonable from an engineering and availability perspective. The benefits, disadvantages, risks, and power plant relevance of each configuration over the baseline DEMO design are discussed.

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“…The ITER FW panels are designed to be individually exchanged by remote handling in-vessel. However, even one month into a DEMO shutdown the gamma dose in-vessel is predicted to be 2 kGy/hr, making a FW in-vessel replacement operation almost inconceivable [16]. Possible exceptions could be limited regions such as the TFW; by making this part of an upper port "plug" it might be exchanged while retaining the inboard and outboard blanket segments in place.…”

Section: Fw Conceptsmentioning

confidence: 99%

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Barrett

Ellwood

Pérez

et al. 2016

Fusion Engineering and Design

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The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing.

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Overview of progress on the European DEMO remote maintenance strategy

Cited by 36 publications

References 6 publications

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Exploring a broad spectrum of design options for DEMO

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

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