C. Koehly

ORCID: 0000-0001-5829-832X
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About
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Research Areas
  • Fusion materials and technologies
  • Nuclear reactor physics and engineering
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Nuclear Materials and Properties
  • Nuclear Engineering Thermal-Hydraulics
  • Metallurgical Processes and Thermodynamics
  • Advanced materials and composites
  • Intermetallics and Advanced Alloy Properties
  • Additive Manufacturing Materials and Processes
  • Particle accelerators and beam dynamics
  • Vibration and Dynamic Analysis
  • Nanofluid Flow and Heat Transfer
  • Fluid Dynamics and Turbulent Flows

Karlsruhe Institute of Technology
2011-2024

FZI Research Center for Information Technology
2007-2008

Tokamak power plants are studied with advanced and conservative design philosophies to identify the impacts on resulting designs provide guidance critical research needs. Incorporating updated physics understanding using more sophisticated engineering analysis, tokamak configurations have developed a credible basis compared older studies. The configuration assumes self-cooled lead lithium blanket concept SiC composite structural material 58% thermal conversion efficiency. This plasma has...

10.13182/fst14-794 article EN Fusion Science & Technology 2014-12-10

AbstractARIES-ACT2 is a conventional tokamak power plant conceptual design that uses dual-coolant lead-lithium (DCLL) blanket concept with RAFS (reduced-activation ferritic steel) first-wall (FW) and structure. The the first fully integrated study of DCLL in plant. major engineering efforts were to develop credible configuration can meet aggressive maintenance goals achieve high availability maintainability; tritium breeding requirements reasonable helium Pb-17Li cooling schemes remove...

10.13182/fst14-798 article EN Fusion Science & Technology 2014-12-10

The current reference concept for a European liquid metal test blanket module (TBM) ITER is water-cooled lead lithium (WCLL) blanket. alloy lead-lithium (PbLi) used as breeder, neutron multiplier, and heat carrier. Pressurized water cools the structure breeding zone by large number of cooling pipes immersed in metal. spatial distribution these interfering manifolds critical issue. Efficient removal from has to be ensured avoid local hotspots fluid or walls. highest velocities occur feeding...

10.1016/j.fusengdes.2023.113753 article EN cc-by-nc-nd Fusion Engineering and Design 2023-04-19

In the frame of EUROfusion breeding blanket research activities, water cooled lead lithium (WCLL) is considered as reference liquid metal design to be tested in ITER and used a DEMO reactor. The blankets represents major challenge for fusion reactor engineering because performance requirements severe operating conditions terms heat load neutron flux. Liquid alloys such lead-lithium, PbLi, are breeder material, due their content required tritium production, transfer medium large thermal...

10.1088/1741-4326/ac18dc article EN Nuclear Fusion 2021-07-29

AbstractARIES-ACT1 engineering design efforts were devoted to developing a credible configuration that allows for rapid removal of full-power core sectors followed by disassembly in hot cells during maintenance. The power evolved with the main objective achieving high performance while maintaining attractive features and configuration, maintenance, fabrication processes. To achieve availability maintainability fusion plant, components sector, including inboard outboard first wall...

10.13182/fst14-797 article EN Fusion Science & Technology 2014-12-10

Liquid metal flows exposed to intense magnetic fields play a fundamental role in the development of blankets for nuclear fusion reactors, where they serve produce plasma-fuel component tritium and transport generated heat. When liquid circulates blanket, it interacts with plasma-confining field leading induction electric currents. Electromagnetic forces thermal buoyancy affect significantly velocity pressure distributions. The resulting magneto-convective flow has peculiar features that have...

10.1016/j.fusengdes.2024.114325 article EN cc-by-nc-nd Fusion Engineering and Design 2024-03-13

Abstract Numerical simulations have been carried out in support of an experimental campaign conducted the MEKKA laboratory at KIT. The aim is investigating liquid metal heat transfer with imposed magnetic field a model geometry relevant for study water cooled lead lithium blankets fusion reactors. In breeding zone this blanket concept, cooling pipes are immersed which convective motion occurs due to significant temperature gradients. test-section features rectangular box containing two...

10.1007/s00231-023-03350-2 article EN cc-by Heat and Mass Transfer 2023-06-05

The dual-coolant lead lithium (DCLL) blanket in which the eutectic lead-lithium alloy is used as tritium breeder and coolant a promising concept for applications fusion power plants. interaction of moving electrically conducting liquid metal with plasma-confining magnetic field induces electric currents creates strong electromagnetic Lorentz forces opposing flow. This may to high magnetohydrodynamic (MHD) pressure drops. Efficient cooling requires sufficiently flow velocity and, under these...

10.1080/15361055.2017.1350477 article EN Fusion Science & Technology 2017-08-22

In order to investigate the fundamental features of magnetohydrodynamic (MHD) channel flows, a closed liquid-metal circuit has been designed and manufactured in MEKKA laboratory at Karlsruhe Institute Technology. This loop, which uses GaInSn as model fluid, provides flexible tool for studying properties MHD flows testing techniques measuring electric potential velocity later use during experiments ITER test blanket modules. Of particular interest is, instance, investigation stability laminar...

10.1109/tps.2011.2177864 article EN IEEE Transactions on Plasma Science 2012-01-06

* E-mail: christina.koehly@kit.eduNote — Some figures may be in color only the electronic version.

10.1080/15361055.2019.1607705 article EN Fusion Science & Technology 2019-05-10

The present paper gives an overview of liquid metal research activities performed in recent years at the Karlsruhe Institute Technology (KIT). work is motivated by applications blankets for a DEMO fusion reactor where lead lithium (PbLi), which serves as neutron multiplier and tritium breeder, interacts with plasma-confining magnetic field it flows blanket covering inner walls reactor. Liquid magnetohydrodynamic (MHD) KIT supports design through theoretical experimental investigations....

10.1016/j.fusengdes.2024.114195 article EN cc-by-nc Fusion Engineering and Design 2024-01-27

In 2008–2009 experiments have been performed to investigate liquid metal magnetohydrodynamic (MHD) flows in a scaled mock-up of helium cooled lead lithium (HCLL) blanket. order improve the mechanical stiffness HCLL blanket modules design stiffening plate between two hydraulically connected breeder units (BUs) has later modified. former passed from one BU into adjacent by flowing through narrow gap that extended along entire width BU. most recent this opening replaced series smaller gaps....

10.1016/j.fusengdes.2016.11.012 article EN cc-by-nc-nd Fusion Engineering and Design 2017-01-07

Previous conceptual design studies for liquid-metal (LM) cooled blankets of a fusion power plant often omit details the complete flow distribution network required to bring coolant into and out blanket, especially manifolding transition from small number feed pipes sometimes large parallel channels within actively heated part core. Manifolding can induce 3-D magnetohydrodynamics (MHD) currents therefore dominate pressure distributions entire which is problematic designs with electrically...

10.1109/tps.2014.2304072 article EN IEEE Transactions on Plasma Science 2014-02-17

Previous conceptual design studies for liquid-metal (LM) cooled blankets of a fusion power plant often omit details the complete flow distribution network required to bring coolant into and out blanket, especially manifolding transition from small number feed pipes sometimes large parallel channels within actively heated part core. Manifolding can induce 3D MHD currents therefore dominate pressure distributions entire which is problematic designs with electrically insulated channels. Within...

10.1109/sofe.2013.6635368 article EN 2013-06-01
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