Conveners
Fusion Materials and Neutron Sources: FTP/4
- Gabriel Marbach (France)
Mr
Yuji Hatano
(Japan)
12/10/2012, 16:40
FTP - Fusion Technology and Power Plant Design
Oral Presentation
Tritium (T) inventory in tungsten (W) after neutron (n) irradiation is an important safety problem because radiation defects trap hydrogen isotopes. Therefore, deuterium (D) retention in n-irradiated W has been examined in Japan/US joint project TITAN. In this project, small W disks were irradiated in High Flux Isotope Reactor, Oak Ridge National Laboratory at coolant temperature (ca. 50...
Mr
Mark Gilbert
(UK)
12/10/2012, 17:00
FTP - Fusion Technology and Power Plant Design
Oral Presentation
The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. Not only do the neutrons bombarding the materials induce atomic displacement cascades, leading to the accumulation of structural defects, but they also initiate nuclear reactions, which cause...
Mr
Hiroo Kondo
(Japan)
12/10/2012, 17:20
FTP - Fusion Technology and Power Plant Design
Oral Presentation
Construction and initial performance tests of EVEDA (Engineering Validation and Engineering Design Activities) Lithium Test Loop (ELTL) were completed and therefore one of the major milestones in the engineering validation toward IFMIF (International Fusion Materials Irradiation Facility) was accomplished. The ELTL, which holds 2.5-ton Li, is a proto-type of a Li target facility of the IFMIF...
Mr
Ellappan Rajendrakumar
(India)
12/10/2012, 17:40
FTP - Fusion Technology and Power Plant Design
Oral Presentation
FTP/4-4Ra: Status of LLCB TBM R&D Activities in India
The development of Lead-Lithium Ceramic Breeder (LLCB) blanket is being performed as the primary candidate of Indian Test Blanket Module (TBM) program towards DEMO reactor. The LLCB TBM will be tested from the first phase of ITER operation (H-H phase) in one-half of a ITER port no-2. Neutronic calculations for the above design of LLCB TBM...
Mr
Jan Fikar
(Switzerland)
12/10/2012, 18:00
FTP - Fusion Technology and Power Plant Design
Oral Presentation
FTP/4-5Ra: Optimisation of a Nanostructured ODS Ferritic Steel Fabrication towards Improvement of its Plasticity
In order to increase the operation temperature of the high-chromium reduced activation steels foreseen in applications of fusion reactors, ferritic steels containing 12 to 14% Cr in weight and reinforced with a dispersion of nano-oxides are being under development. The nano-oxides...
Mr
Englen Azizov
(Russian Federation)
12/10/2012, 18:20
FTP - Fusion Technology and Power Plant Design
Oral Presentation
Development of tokamak based fusion neutron sources and fusion-fission hybrids for nuclear fuel production and nuclear waste transmutation has been initiated in Russia to accelerate implementation of modern magnetic fusion technologies.
Various devices realizing intense DT fusion from 1 MW up to 100 MW have been considered and passed the pre-conceptual design level. Those include...
IAEA - Nuclear Fusion Representative,
Prize Winners
12/10/2012, 18:40
Oral Presentation
