Results 1 to 10 of about 2,582,903 (100)
Nuclear Materials and Energy, 2016 Lithium titanate with excess lithium (Li2+xTiO3+y) is one of the most promising candidates among advanced tritium breeders for demonstration power plant reactors because of its good tritium release characteristics.
Tsuyoshi Hoshino
doaj +4 more sources
One‐step fabrication of Li2TiO3 ceramic pebbles using pulsed YAG laser [PDF]
Journal of the American Ceramic Society, Volume 106, Issue 10, Page 5735-5742, October 2023., 2023 One‐step fabrication of Li2TiO3 pebble using pulsed YAG laser Abstract A large amount of Li‐containing ceramic breeder pebbles is packed in the solid breeding blanket of a nuclear fusion reactor. Several pebble fabrication technologies have been proposed in previous studies, including wet process, emulsion method, extrusion spheronization, additive ...
Keisuke Mukai
wiley +3 more sources
Current status and future perspectives of EU ceramic breeder development [PDF]
Fusion engineering and design, 2021 Biphasic ceramic pebbles, consisting of Li4SiO4 and Li2TiO3, are being developed as the EU reference tritium breeding material for ITER and DEMO. A modified melt-based process for the pebble fabrication was established and optimised with regard to the ...
O. Leys, J. Leys, R. Knitter
semanticscholar +2 more sources
Chemistry Section and Section of Institute of Chemical Physics. Book of AbstractsAnna Ansone +3 more
openaire +2 more sources
Journal of Nuclear Materials, 2022 The reduced activation ferritic-martensitic steel EUROFER is a prime candidate for fusion structural applications. In the advanced helium-cooled pebble bed blanket concept of DEMO, this steel is in direct contact with Li-ceramics pebbles and experiences ...
E. Gaisina +5 more
semanticscholar +1 more source
Fusion Materials Development at Forschungszentrum Jülich
Advanced Engineering Materials, Volume 22, Issue 6, June 2020., 2020 In fusion material research, the focus has been twofold‐plasma facing and structural materials allowing to withstand the extreme conditions such as neutron bombardment and high heat fluxes. In this contribution, the background for the choice of tungsten as first wall material is given and the advanced materials developed at Forschungszentrum Jülich ...
Jan Willem Coenen
wiley +1 more source
Compilation of Existing Neutron Screen Technology
Science and Technology of Nuclear Installations, Volume 2014, Issue 1, 2014., 2014 The presence of fast neutron spectra in new reactors is expected to induce a strong impact on the contained materials, including structural materials, nuclear fuels, neutron reflecting materials, and tritium breeding materials. Therefore, introduction of these reactors into operation will require extensive testing of their components, which must be ...
N. Chrysanthopoulou +4 more
wiley +1 more source
Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities
Science and Technology of Nuclear Installations, Volume 2013, Issue 1, 2013., 2013 The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing ...
Nick R. Soelberg +7 more
wiley +1 more source
Decay Heat Removal in GEN IV Gas‐Cooled Fast Reactors
Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009 The safety goal of the current designs of advanced high‐temperature thermal gas‐cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct‐cycle gas‐cooled fast reactor (GFR ...
Lap-Yan Cheng +2 more
wiley +1 more source
Gas‐Cooled Fast Reactor: A Historical Overview and Future Outlook
Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009 A review is given of developments in the area of Gas‐Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants.
W. F. G. van Rooijen, Guglielmo Lomonaco
wiley +1 more source