Results 61 to 70 of about 13,799 (192)

Special Libraries, January 1925 [PDF]

, 1923
Volume 16, Issue 1https://scholarworks.sjsu.edu/sla_sl_1925/1000/thumbnail ...
Special Libraries Association
core   +3 more sources

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

Nuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

An optimized BSCCO/Ag resonator coil for utility use [PDF]

, 2000
AC coils made with BSCCO-2223/Ag tapes and operating in liquid nitrogen have a potential for power related applications, e.g., inductors, transformers and current limiters.
Broeren, B., Damstra, G.C., Godeke, A., Haken, B. ten, Kate, H.H.J. ten, Klein Schiphorst, P., Krooshoop, H.J.G., Rutten, G., Scholten, A., Shevchenko, O.A., Spoorenberg, C.J.G.   +10 more
core   +2 more sources

W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket

Nuclear Fusion
In the framework of the activities coordinated by the EUROfusion consortium, the Water thermal-HYDRAulic (W-HYDRA) experimental platform is being built at the ENEA Brasimone Research Centre in order to support the development of the Water-Cooled Lead ...
P. Arena, A. Del Nevo, M. Eboli, B. Gonfiotti, P. Maccari, R. Marinari, A. Tincani, N. Badodi, G. Bongiovì, I. Catanzaro, F. Galleni, C. Risi, L.L. Sanasi, A. Tarallo, A. Vannoni   +14 more
doaj   +1 more source

Spartan Daily, May 11, 2016 [PDF]

, 2016
Volume 146, Issue 41https://scholarworks.sjsu.edu/spartan_daily_2016/1039/thumbnail ...
San Jose State University, School of Journalism and Mass Communications
core   +2 more sources

MHD flow and heat transfer in model geometries for WCLL blankets

Fusion Engineering and Design, 2017
Abstract In the water cooled lead lithium (WCLL) blanket liquid lead lithium PbLi is used as breeder, neutron multiplier, and as heat transfer medium. The released heat is removed by water that flows at a pressure of 155 bar through cooling pipes immersed in the liquid-metal pool.
Bühler, L., Mistrangelo, C.
openaire   +2 more sources

Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]

Nuclear Technology and Radiation Protection
This paper presents a dose rate assessment within the DEMO fusion reactor's auxiliary premises, focusing on activated water and Activated Corrosion Products as primary radiation sources.
Sereda Svitlana, Sereda Serhii, Ciattaglia Sergio, Nosovsky Anatoly, Gulik Volodymyr   +4 more
doaj   +1 more source

Special Libraries, September 1933 [PDF]

, 1932
Volume 24, Issue 8https://scholarworks.sjsu.edu/sla_sl_1933/1007/thumbnail ...
Special Libraries Association
core   +5 more sources

System for producing chroma signals [PDF]

, 1977
A method for obtaining electronic chroma signals with a single scanning-type image device is described. A color multiplexed light signal is produced using an arrangement of dichroic filter stripes.
Lipoma, P. C., Vorhaben, K. H.
core   +1 more source

Molecular Dynamics Simulations of Lead and Lithium in Liquid Phase [PDF]

, 2011
Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. Extracting dynamic and structural properties of liquid LiPb mixtures via molecular dynamics simulations, represent a crucial step for multiscale modeling efforts ...
Cuesta Lopez, Santiago, Fraile García, Alberto, Perlado Martín, José Manuel   +2 more
core   +3 more sources