The design progress in a compact low aspect ratio (low A) DEMO reactor, ‘SlimCS’, and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m−2 or lower, which can be a critical constraint for determining a handling power of DEMO.

No abstract

No abstract

Abstract. Deuteron irradiation experiments were performed to measure two kinds of data for IFMIF accelerator structural materials. One is a measurement of deuteron-induced activation cross sections for prospective candidate materials, i.e., aluminum, vanadium, chromium, manganese, iron, nickel, copper, tantalum, tungsten and gold, in the energy range of 14-49 MeV. The other is a measurement of deuteron-induced activities of nuclide produced in SS316 and F82H by 39.5 MeV deuteron. It is found that most measured cross sections correspond with TALYS calculations rather than ACSELAM and it is confirmed that the activities in SS316 and F82H can be nearly evaluated within the accuracy of the experimental errors by using the present measured cross section data.

No abstract