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MHD flow and heat transfer in model geometries for WCLL blankets
Fusion Engineering and Design, 2017 Abstract In the water cooled lead lithium (WCLL) blanket liquid lead lithium PbLi is used as breeder, neutron multiplier, and as heat transfer medium. The released heat is removed by water that flows at a pressure of 155 bar through cooling pipes immersed in the liquid-metal pool.
L Bühler, C Mistrangelo
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Preliminary RAMI analysis of WCLL blanket and breeder systems
Fusion Engineering and Design, 2015Abstract DEMO will be a prototype fusion reactor designed to prove the capability to produce electrical power in a commercially acceptable way. One of the key factors in that endeavor is the achievement of certain level of plant availability. Therefore, RAMI (Reliability, Availability, Maintainability and Inspectability) will be a key element in the ...
Jose Manuel Arroyo +4 more
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Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO
Fusion Engineering and Design, 2019 The Breeding Blanket (BB) First Wall (FW) is the first boundary separating the fusion plasma and its energetic particles from the rest of a Tokamak. The heat load specifications at different poloidal positions are reviewed according to the maximum heat ...
Kecheng Jiang +2 more
exaly +2 more sources
An overview on tritium permeation barrier development for WCLL blanket concept
Journal of Nuclear Materials, 2004The reduction of tritium permeation through blanket structural materials and cooling tubes has to be carefully evaluated to minimise radiological hazards. A strong effort has been made in the past to select the best technological solution for the realisation of tritium permeation barriers (TPB) on complex structures not directly accessible after the
CIAMPICHETTI, ANDREA +2 more
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Design of an in-pile device for testing of WCLL double wall tubes
Fusion Engineering and Design, 2000Abstract The present paper describes irradiation devices proposed by SCK CEN to test segments of water cooled lithium–lead blankets (WCLL), and in particular their double-wall tubes (DWT), under irradiation in the BR2 reactor. The purpose of the first experiment is to assess the efficiency of a tritium permeation barrier (TPB) coating at the outer ...
Philippe Benoit +2 more
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Neutronic design issues of the WCLL and HCPB power plant models
Fusion Engineering and Design, 2003Abstract This work addresses neutronic design issues of the two near term reactor models of the EU Power Plant Conceptual Study (PPCS) employing the water cooled lithium lead (WCLL) and the helium cooled pebble bed (HCPB) blankets for the tritium and the power production.
Chen, Y., Fischer, U., Pereslavtsev, P.
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Pb–17Li/water interaction in DEMO WCLL blanket: water micro-leaks
Fusion Engineering and Design, 2003Abstract The interaction between pressurised water and liquid Pb–17Li is a topical issue for the WCLL blanket concept and needs to be studied in detail because of the potentially significant effect on the reliability and safety of the blanket. Particularly, it seems important from the design point of view to deeply investigate the consequences of ...
I. RICAPITO +2 more
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Magnetohydrodynamic velocity and pressure drop in manifolds of a WCLL TBM
Nuclear Fusion, 2021C. Mistrangelo +3 more
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Maintenance Procedure on WCLL Ancillary System–Virtual Reality Application
Technologies such as Augmented Reality and Virtual Reality (AR-VR) are changing the way to design the models. These technologies prove useful across all design phases, yet their greatest application lies in supporting the entire life cycle of a system.Bonavolontà, Ugo +2 more
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