Results 111 to 120 of about 3,747 (225)

Fusion energy from the Moon for the twenty-first century [PDF]

open access: yes
It is shown in this paper that the D-He-3 fusion fuel cycle is not only credible from a physics standpoint, but that its breakeven and ignition characteristics could be developed on roughly the same time schedule as the DT cycle.
Cameron, E. N.   +5 more
core   +1 more source

High-dose neutron irradiation of beryllium and titanium beryllide: Summary and outlook

open access: yesNuclear Materials and Energy
The irradiation experiment conducted in the HFR material testing reactor, under conditions simulating the operating environment of the DEMO breeding blanket, along with subsequent post-irradiation examinations (PIEs) of irradiated beryllium-based ...
Vladimir Chakin   +15 more
doaj   +1 more source

Nucleation of Helium in Liquid Lithium at 843 K and High Pressures. [PDF]

open access: yesMaterials (Basel), 2022
Martí J   +5 more
europepmc   +1 more source

Neutronics Simulations for DEMO Diagnostics. [PDF]

open access: yesSensors (Basel), 2023
Luís R   +13 more
europepmc   +1 more source

Commercial objectives, technology transfer, and systems analysis for fusion power development [PDF]

open access: yes
Fusion is an inexhaustible source of energy that has the potential for economic commercial applications with excellent safety and environmental characteristics.
Dean, Stephen O.
core   +1 more source

Breeding blanket development; Tritium release from breeder

open access: yesBreeding blanket development; Tritium release from breeder
核融合炉ブランケットを設計するためには、微小球を用いたブランケット構造体の中性子照射に関する工学的データが必要不可欠である。工学的データのうち、トリチウム生成放出特性は、最も重要なデータの1つである。このため、トリチウム増殖材料の候補材であるチタン酸リチウム(Li$_{2}$TiO$_{3}$)微小球からのトリチウム生成放出試験を行い、トリチウム放出特性に対するスイープガス流量,照射温度,スイープガス中の水素添加量,熱中性子束の変化等の効果について調べた。本試験の結果、(1)Li$_{2}$TiO$_{3}$微小球充填体の外壁温度が100$^{\circ}$C以上になった時、トリチウム放出が観測された。また、充填体の外壁温度が300$\sim$400$^{\circ}$Cのとき、トリチウム生成 ...
openaire  

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