Results 21 to 30 of about 9,751 (308)
ITER solid breeder blanket materials database [PDF]
, 1993 The databases for solid breeder ceramics (Li{sub 2},O, Li{sub 4}SiO{sub 4}, Li{sub 2}ZrO{sub 3} and LiAlO{sub 2}) and beryllium multiplier material are critically reviewed and evaluated. Emphasis is placed on physical, thermal, mechanical, chemical stability/compatibility, tritium, and radiation stability properties which are needed to assess the ...
Billone, M. C. +5 more
openaire +2 more sources
Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]
, 2016 © 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I. +6 more
core +4 more sources
Annihilation kinetics of irradiation defects in promising tritium breeding pebbles
Nuclear Materials and Energy, 2021 Lithium-based tritium breeding materials will be adopted to produce tritium in the D-T fusion reactor. Li2TiO3 and Li4SiO4 pebbles have been proposed as candidates in water-cooled ceramic breeder blanket (WCCB) and helium-cooled ceramic breeder blanket ...
Baolong. Ji +6 more
doaj +1 more source
Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR
Energies, 2021 A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as
Kecheng Jiang +6 more
doaj +1 more source
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 +12 more
doaj +1 more source
Energies, 2021 In the tritium breeding blanket of nuclear fusion reactors, the heat transfer behavior and thermal-mechanical response of the tritium breeder pebble bed are affected by the inner packing structure, which is crucial for the design and optimization of a ...
Baoping Gong +5 more
doaj +1 more source
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 +4 more
openaire +1 more source
Frontiers in Energy Research, 2021 Tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation, and neutron shielding.
Shen Qu +6 more
doaj +1 more source
Specifications for a coupled neutronics thermal-hydraulics SFR test case [PDF]
, 2017 Coupling neutronics/thermal-hydraulics calculations for the design of nuclear reactors is a growing trend in the scientific community. This approach allows to properly represent the mutual feedbacks between the neutronic distribution and the thermal ...
TASSONE, ALESSANDRO
core +1 more source
Nuclear Materials and Energy, 2023 The advancement of sophisticated packed beds has significant implications for the development of new equipment for associated industries. Determining the heat transfer and fluid flow properties of the functional material in the form of a pebble bed is ...
Chirag Sedani +2 more
doaj +1 more source