High-power liquid-lithium jet target for neutron production

S Halfon, A Arenshtam, D Kijel, M Paul… - Review of scientific …, 2013 - pubs.aip.org
A compact liquid-lithium target (LiLiT) was built and tested with a high-power electron gun at
the Soreq Nuclear Research Center. The lithium target, to be bombarded by the high …

IFMIF/EVEDA lithium test loop: design and fabrication technology of target assembly as a key component

H Kondo, T Furukawa, Y Hirakawa, K Nakamura… - Nuclear …, 2011 - iopscience.iop.org
The engineering validation and engineering design activity (EVEDA) for the International
Fusion Materials Irradiation Facility (IFMIF) is proceeding as one of the ITER broader …

Completion of IFMIF/EVEDA lithium test loop construction

H Kondo, T Furukawa, Y Hirakawa, H Iuchi… - Fusion Engineering and …, 2012 - Elsevier
The EVEDA Li test loop (ELTL) successfully completed its construction and installation of a
total of 2.5-ton Li in the frame work of the IFMIF/EVEDA as one of the ITER-BA. Design for …

Design of purification loop and traps for the IFMIF/EVEDA Li test loop: design of cold trap

H Kondo, T Furukawa, Y Hirakawa, H Iuchi… - Fusion engineering and …, 2011 - Elsevier
Engineering Validation and Engineering Design Activities (EVEDA) for the International
Fusion Materials Irradiation Facility (IFMIF) were started under a collaborative international …

Orientation dependences of the Fe-Li solid-liquid interface properties: Atomistic simulations

X Gan, S Xiao, H Deng, X Li, W Hu - Journal of Alloys and Compounds, 2016 - Elsevier
Abstract The Fe (110)-Li and Fe (111)-Li solid-liquid interfaces are investigated using
molecular dynamics simulations (MD), and the results are detailedly compared with each …

IFMIF's new design: Status after 2 years of the EVEDA project

P Garin, M Sugimoto - Journal of nuclear materials, 2011 - Elsevier
IFMIF is a major installation in the fusion programme to irradiate and characterize the fusion
materials, under intense neutron field, necessary for contributing to the development of …

Tritium removal by Y hot trap for purification of IFMIF Li target

Y Edao, S Fukada, S Yamaguchi, Y Wu… - Fusion engineering and …, 2010 - Elsevier
The use of Li is expected for a flowing target in the International Fusion Materials Irradiation
Facility (IFMIF) for high-intensity neutron generation. Tritium (T) of by-product is removed by …

Impurity activation and transfer of activation products in the liquid Li loop of fusion neutron source

S Kenjo, M Oyaidzu, M Ohta, S Kwon, K Ochiai… - Fusion Engineering and …, 2024 - Elsevier
In the Li loops of IFMIF-like fusion neutron sources, various types of radionuclides are
generated and deposited in the Li loop components depending on conditions. This study …

Safety concept of the IFMIF/EVEDA lithium test loop

T Furukawa, H Kondo, Y Hirakawa, S Kato… - Fusion engineering and …, 2011 - Elsevier
In order to obtain engineering data on the lithium target system, which is the neutron source
of the International Fusion Material Irradiation Facility (IFMIF), design and fabrication of the …

Progress in IFMIF engineering validation and engineering design activities

R Heidinger, J Knaster, H Matsumoto… - Fusion Engineering and …, 2013 - Elsevier
Abstract The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design
and Engineering Validation Activities (EVEDA) are being developed in a joint project in the …