Experimental study on corrosion and precipitation in non-isothermal Pb-17Li system for development of liquid breeder blanket of fusion reactor
Author:
Publisher
IOP Publishing
Subject
General Physics and Astronomy
Link
http://stacks.iop.org/1742-6596/877/i=1/a=012001/pdf
Reference18 articles.
1. An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dual-coolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step
2. Study on fabrication method of lithium alloys with metal grains
3. Experimental Study on Chemical Behaviors of Non-Metal Impurities in Pb, Pb-Bi and Pb-Li by Temperature Programmed Desorption Mass Spectrometer Analysis
4. Boiling points of liquid breeders for fusion blankets
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1. Compatibility of FeCrAlMo with flowing PbLi at 500°-650 °C;Journal of Nuclear Materials;2020-01
2. Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities;Fusion Science and Technology;2019-05-10
3. Automation and interlock system design for Pb-Li liquid-metal purification experimental facility;Fusion Engineering and Design;2019-04
4. Design, development and testing of prototype cold trap for Pb-16Li purification;Fusion Engineering and Design;2018-12
5. Corrosion–erosion and mass transfer dynamic behaviors of reduced activation ferritic/martensitic steel in a nonisothermal Pb-17Li system;Fusion Engineering and Design;2018-11
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