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Kwon, S.*; Sato, Satoshi; Kasada, Ryuta*; Konishi, Satoshi*
Fusion Science and Technology, 64(3), p.599 - 603, 2013/09
Times Cited Count：2 Percentile：17.48(Nuclear Science & Technology)Tritium production/breeding behavior in LiPb blanket module was evaluated by neutron transport code MCNP with nuclear cross-section data from FENDL-2.1 libraries. The calculation results were suggested that the sufficient TBR can be obtained in the SiC-LiPb blanket concept. A proper integral experiment on LiPb with DT neutrons in a small test module was evaluated. Also, tritium breeding ratio, tritium production ratio, proper neutron shielding material and nuclear heating in the module were evaluated. With the results of TPR and actual neutron generation devices, we have proposed the plan of the integral experiment and measurable tritium amount.
Pitcher, C. S.*; Barnsley, R.*; Bertalot, L.*; Encheva, A.*; Feder, R.*; Friconneau, J. P.*; Hu, Q.*; Levesy, B.*; Loesser, G. D.*; Lyublin, B.*; et al.
Fusion Science and Technology, 64(2), p.118 - 125, 2013/08
Times Cited Count：5 Percentile：36.31(Nuclear Science & Technology)The port-based plasma diagnostic infrastructure on ITER is described, including the port plugs, the interspace support structure and port cell structure. These systems are modular in nature with standardized dimensions. The design of the equatorial and upper port plugs and their modules is discussed, as well as the dominant loading mechanisms. The port infrastructure design has now matured to the point that port plugs are now being populated with multiple diagnostics supplied by a number of ITER partners - two port plug examples are given.
Okumura, Yoshikazu
Fusion Science and Technology, 64(2), p.86 - 95, 2013/08
Times Cited Count：3 Percentile：24.26(Nuclear Science & Technology)Five years have passed since the Broader Approach (BA) activities launched in 2007 under the framework of collaboration between Japan and EURATOM. In a DEMO R&D Building in the IFERC site in Rokkasho, tritium facility, beryllium treatment facility, and microscopic measurement facility were installed in 2010. The tritium was delivered in March 2012. A supercomputer for the simulation of fusion plasmas and other application of the BA activities starts operation in January 2012. It demonstrated LINPAC speeds of more than 1.2 PFlops. Accelerator components for IFMIF/EVEDA are being fabricated in European institutes. The injector is now under commissioning in CEA Saclay, and will be delivered in Rokkasho in March 2013. The IFMIF/EVEDA lithium test loop was constructed in Oarai, Japan, in 2011 and starts operation in May 2012. The JT-60 tokamak is being disassembled and upgraded to an advanced superconducting tokamak JT-60SA. Manufacturing of tokamak components is now in progress.
Oda, Yasuhisa; Kajiwara, Ken; Takahashi, Koji; Sakamoto, Keishi
no journal, ,
Matsumoto, Hiroshi; Knaster, J.*; Heidinger, R.*; Sugimoto, Masayoshi; Ibarra, A.*; Mosnier, A.*; Heinzel, V.*; Massaut, V.*; Micciche, G.*; M
slang, A.*
no journal, ,
The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design and Engineering Validation Activities (EVEDA) started in 2007 under the framework of the Broader Approach (BA) Agreement between EU and Japan with the objective of developing a complete engineering design of the IFMIF together with accompanying sub projects to validate the major elements of the technologies essential for the IFMIF Plant. The validation sub projects include design and construction of the prototype deuteron beam accelerator, Lithium Loop Test Facility, and irradiation test of samples in Rigs for High Flux Test Modules. The recent achievements from these activities will be presented.
Hamaguchi, Dai; Ando, Masami; Tanigawa, Hiroyasu; Kasada, Ryuta*; Nogami, Shuhei*; Abe, Hiroaki*; Hashimoto, Naoyuki*
no journal, ,
Ion irradiation is one of a powerful method for irradiation tests because of their rapid damage production, the absence of induced radioactivity, controllable test conditions such as temperatures and doses, simultaneous introduction of damages and He gases, in order to estimate the fusion neutron irradiation effects on DEMO blanket structural materials. However, ion irradiation test is not suitable enough to acquire mechanical property degradation data since the damage layer tends to be very shallow from the surface. Despite this disadvantage, the method is still a powerful tool to understand the effects especially under high dose irradiations and also synergetic effects with He (and/or H) and damages in terms of microstructural changes. In this presentation, the recent effort on the establishment of methodologies to predict fusion neutron effects under Japanese ITER-BA activity will be reviewed, emphasizing on using the ion irradiation technique.
