Results 271 to 280 of about 1,329 (294)

A STUDY OF PERMEATION BARRIERS FOR Pb17Li BREEDING BLANKETS

1991
Coatings on the surface in contact with Pb17Li can significantly decrease tritium permeation rate through structural steels and tritium inventory in the blanket. For this purpose, compatibility tests of oxidized and aluminized 316L and 1.4914 steels have been carried out up to 500°C in stagnant anisothermal Pb17Li.
A. Terlain, T. Flament, J. Sannier, J.L. Rouault   +3 more
openaire   +1 more source

A Hydrogen Sensor for Liquid-Metal Breeding Blankets

2015
In HCLL (Helium Cooled Lithium Lead) blanket for ITER fusion reactor, an efficient management operation of tritium is necessary, in order to minimize the release of tritium to the environment and to improve the economy of the overall balance of the reactor tritium inventory. In this context, optimization techniques for the measurement of tritium in the
NICOLOTTI, IURI, Utili, M., CANDIDO, LUIGI, ZUCCHETTI, MASSIMO   +3 more
openaire   +3 more sources

Tritium Breeding Capability of Heliotron-H Fusion Reactor Blankets

Journal of Nuclear Science and Technology, 1982
Masao Ohta, Atsuo Iiyoshi
exaly  

European TBM programme: First elements of RoX and technical performance assessment for DEMO breeding blankets

Fusion Engineering and Design, 2020
I Ricapito, F Cismondi, Y Poitevin
exaly  

First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors

Fusion Engineering and Design, 2018
FRANCISCO A Hernández, P Pereslavtsev
exaly  

Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO

Fusion Engineering and Design, 2018
Luigi Candido, Raffaella Testoni, Marco Utili   +2 more
exaly  

Nuclear Design of Heliotron Fusion Reactor Blankets

Journal of Nuclear Science and Technology, 1981
Masao Ohta
exaly  

Materials aspects of breeding blanket design

Journal of Nuclear Materials, 1991
openaire   +1 more source

Neutronics performance evaluation of fast-fission fuel breeding blankets for a fusion–fission hybrid reactor

Fusion Engineering and Design, 2010
Minghuang Wang, Jieqiong Jiang, Yunqing Bai   +2 more
exaly  

The European breeding blankets development and the test strategy in ITER

Fusion Engineering and Design, 2005
Y Poitevin, L V Boccaccini, L Giancarli   +2 more
exaly