Search Results - "Laesser, R"
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Combined use of two supervised learning algorithms to model sea turtle behaviours from tri-axial acceleration data
Published in Journal of experimental biology (23-05-2018)“…Accelerometers are becoming ever more important sensors in animal-attached technology, providing data that allow determination of body posture and movement and…”
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2
Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO
Published in Fusion engineering and design (01-12-2010)“…Europe has developed two reference tritium breeder blankets concepts that will be tested in ITER under the form of Test Blanket Modules: (i) the Helium-Cooled…”
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Journal Article Conference Proceeding -
3
The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals
Published in Journal of nuclear materials (30-04-2009)“…The EU fusion materials modelling programme was initiated in 2002 with the objective of developing a comprehensive set of computer modelling techniques and…”
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4
ITER fuel cycle R&D: Consequences for the design
Published in Fusion engineering and design (01-02-2006)“…The ITER fuel cycle is designed to handle considerable flow rates of tritium with high flexibility and reliability; experimental work is ongoing to validate…”
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5
Fusion materials development program in the broader approach activities
Published in Journal of nuclear materials (30-04-2009)“…Breeding blankets are the most important components in DEMO. The DEMO blanket has to withstand high neutron flux typically 15–30 dpa/year under continuous…”
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Journal Article Conference Proceeding -
6
Design progress for the ITER torus and neutral beam cryopumps
Published in Fusion engineering and design (01-10-2011)“…The ITER torus and neutral beam cryopumps are complex vacuum pumps which will be designed to the build-to-print level stage for the call for tender for…”
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Journal Article Conference Proceeding -
7
The European integrated materials and technology programme in fusion
Published in Journal of nuclear materials (01-08-2004)“…The paper reviews the present EU long-term programme, which is focused on the R&D of the materials and key technologies needed for the DEMO reactor. The…”
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Ferritic–Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validation
Published in Journal of nuclear materials (30-04-2009)“…The Helium-Cooled Lithium-Lead and the Helium-Cooled Pebble Bed are the two breeding blankets concepts for the DEMO reactor which have been selected by EU to…”
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Journal Article Conference Proceeding -
9
The European breeding blankets development and the test strategy in ITER
Published in Fusion engineering and design (01-11-2005)“…In Europe, two breeding blankets are currently developed for DEMO reactor specifications, corresponding to two different research lines, one using a liquid…”
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10
The ancillary systems of the European test blanket modules: Configuration and integration in TIER
Published in Fusion engineering and design (01-12-2010)“…The conceptual design of the ancillary systems of the European Test Blanket Modules (TBMs), namely the PbLi circuit, the Helium Cooling Systems (HCSs), the…”
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11
Structural materials development and databases
Published in Fusion engineering and design (01-02-2006)“…Fusion plants will have a large scale and therefore need a high availability and reliability to generate electricity economically. The materials total life…”
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12
EU fuel cycle development priorities for ITER
Published in Fusion engineering and design (01-10-2007)“…The paper describes the key elements of the EU fuel cycle development for ITER. The programme is now closely focused on the systems allocated to the EU for…”
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Journal Article Conference Proceeding -
13
Protection of the primary circuits and effect on the design of the inner deuterium/tritium fuel cycle of ITER
Published in Fusion engineering and design (01-11-2005)“…The confinement of tritium within its respective processing systems is clearly one of the most important safety objectives for fusion reactors. Consequently,…”
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Journal Article Conference Proceeding -
14
Experience gained during the modification of the Caprice system to Caper
Published in Fusion engineering and design (01-11-2000)“…The experimental facility Caprice was designed to comply with the requirements for clean-up of tokamak exhaust gases. In the last 3 years simulated fusion…”
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Journal Article Conference Proceeding -
15
Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials
Published in Journal of nuclear materials (01-08-2007)“…Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from…”
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16
Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&D activities
Published in Journal of nuclear materials (01-10-2011)“…Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium–Lead and the Helium-Cooled…”
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Journal Article Conference Proceeding -
17
Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&; amp; D activities
Published in Journal of nuclear materials (01-10-2011)“…Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium-Lead and the Helium-Cooled…”
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Journal Article -
18
Gas species, their evolution and segregation through the ITER vacuum systems
Published in Vacuum (31-05-2012)“…This paper takes the ITER fueling requirements and current knowledge of gas balance and exhaust from operating tokamaks to predict all likely gas inputs into…”
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19
Modelling irradiation effects in fusion materials
Published in Fusion engineering and design (01-10-2007)“…We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future…”
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Journal Article Conference Proceeding -
20
Design of the ITER torus prototype cryopump
Published in Fusion engineering and design (01-10-2007)“…Forschungszentrum Karlsruhe (FZK) is developing the ITER prototype torus exhaust pumping system, comprising eight identical cryosorption pumps to provide a…”
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Journal Article Conference Proceeding