Results 1 to 10 of about 138,394 (238)

Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR

Theoretical and Applied Mechanics Letters, 2019
: The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP).
Songlin Liu, Xiaoman Cheng, Xuebin Ma, Lei Chen, Kecheng Jiang, Xia Li, Hui Bao, Jichao Wang, Wanjing Wang, Changhong Peng, Peng Lu, Min Li, Kai Huang   +12 more
doaj   +2 more sources

Remote handling of DEMO breeder blanket segments: Blanket transporter conceptual studies

Fusion Engineering and Design, 2017
Abstract As part of the EUROfusion DEMO programme, RACE has been developing a set of concept designs for remote maintenance systems. The tritium breeding blankets will require periodic replacement via the upper vertical ports at the top of the vacuum vessel.
Keep, Jonathan, Wood, Steve, Gupta, Neelam, Coleman, Matti, Loving, Antony   +4 more
openaire   +2 more sources

Oxidation behaviour of EUROFER-97 under simulated water-cooled lithium lead breeder blanket conditions [PDF]

npj Materials Degradation
The effect of water chemistry, surface condition, alkalizing agent (LiOH vs. KOH), and Zn addition was investigated at 300 °C on the oxidation behaviour of reduced activation ferritic martensitic (RAF/M) EUROFER-97.
Liberato Volpe, Dora Capone, Peter Andresen, Eric Prestat, Fabio Scenini   +4 more
doaj   +2 more sources

Design of the CIEMAT Corrosion Loop for Liquid Metal Experiments

Applied Sciences, 2022
The main components of a liquid breeder blanket in a fusion power reactor are lead lithium alloy (PbLi) and the steel structure in which the liquid is enclosed (EUROFER). Several compatibility tests have shown that structural materials always suffer from
Elisabetta Carella, David Rapisarda, Stephan Lenk   +2 more
doaj   +1 more source

Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts

Applied Sciences, 2023
An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev, Francisco Alberto Hernández, Ivo Moscato, Jin Hun Park   +3 more
doaj   +1 more source

Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

Fluids, 2021
In blankets of a fusion power reactor, liquid metal (LM) breeders, such as pure lithium or lead-lithium alloy, circulate in complex shape blanket conduits for power conversion and tritium breeding in the presence of a strong plasma-confining magnetic ...
Sergey Smolentsev
doaj   +1 more source

Experimental Thermal–Hydraulic Testing of a Mock-Up of the Fuel-Breeder Pin Concept for the EU-DEMO HCPB Breeding Blanket

Journal of Nuclear Engineering, 2022
The fusion program in the Karlsruhe Institute of Technology (KIT) leads the R&D of the DEMO helium-cooled pebble bed (HCPB) breeding blanket within the work package breeding blanket (WPBB) of the Eurofusion Consortium in the European Union (EU).
Ali Abou-Sena, Bradut-Eugen Ghidersa, Guangming Zhou, Joerg Rey, Francisco A. Hernández, Martin Lux, Georg Schlindwein   +6 more
doaj   +1 more source

Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

Nuclear Materials and Energy, 2021
Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO).
Yudong Lu, Minyou Ye, Guangming Zhou, Francisco A. Hernández, Jaakko Leppänen, Yuan Hu   +5 more
doaj   +1 more source

Effect of packing structure on anisotropic effective thermal conductivity of thin ceramic pebble bed

Nuclear Engineering and Technology, 2021
Helium cooled solid breeder blanket as an important blanket candidate of the Tokamak fusion reactor uses ceramic pebble bed for tritium breeding. Considering the poor effective thermal conductivity of the ceramic breeder pebble bed, thin structure of ...
Shuang Wang, Shuai Wang, Bowen Wu, Yuelin Lu, Kefan Zhang, Hongli Chen   +5 more
doaj   +1 more source

Fundamental Study on Fretting Corrosion in Solid Breeder Blanket

Plasma and Fusion Research, 2021
Lithium titanate (Li 2 TiO 3 ) is candidate tritium breeder of the fusion blanket systems. The small pebbles of Li 2 TiO 3 are packed in the blanket box.
Naoki Takahashi, M. Kondo, Jae-Hwan Kim, M. Nakamichi   +3 more
semanticscholar   +1 more source