29th Symposium on Fusion Technology (SOFT 2016)

Session

O1A

Sep 5, 2016, 4:40 PM

Prague Congress Centre

49488. O1A.1 Tritium modeling in HCPB breeder blanket at a system level: a preliminary parametrical approach

Elisabetta Carella (National Fusion Laboratory)

9/5/16, 4:40 PM

H. Fuel Cycle and Breeding Blankets

Oral

Tritium behavior in a breeding blanket is a key design issue because of its impact on safety and fuel-cycle best performance. Nowadays there are only few references and any fully validated tool with predictive capabilities. Considering the difficulty in handling tritium and its fundamental role inside a fusion reactor, it is intended to prepare a simulation tool for tritium transport.In this...

49489. O1A.2 Progress of R&D on advanced tritium breeders for BA activity in EU and Japan

Tsuyoshi Hoshino (Breeding Functional Materials Development Group)

9/5/16, 5:00 PM

H. Fuel Cycle and Breeding Blankets

Oral

Any demonstration power reactor (DEMO), which applies solid breeder blankets, requires “advanced tritium breeders” with high tritium breeding ratios and increased stability at high temperatures. However, the fabrication techniques of advanced tritium breeder pebbles have yet to be established. Therefore, the R&D on the fabrication technologies of the advanced tritium breeders and the...

49490. O1A.3 Design and R&D Activities of Fusion Breeder Blankets in China

Jie Yu (Key Laboratory of Neutronics and Radiation Safety)

9/5/16, 5:20 PM

H. Fuel Cycle and Breeding Blankets

Oral

China has long been active in pushing forward the fusion energy development to the demonstration of electricity generation. Two experts’ meetings were organized in 2014 by Ministry of Science and Technology (MOST) to seriously discuss the China’s fusion roadmap in particular the design and construction of magnetic confinement fusion reactor beyond ITER. As one of the most challenging...

49491. O1A.4 WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Alessandro Del Nevo (ENEA CR Brasimone)

9/5/16, 5:40 PM

H. Fuel Cycle and Breeding Blankets

Oral

Water-Cooled Lithium-Lead Breeding Blanket (WCLL) is considered a candidate option for European DEMO reactor. Starting from previous experiences in the frame of Power Plant Conceptual Studies within EUROfusion Consortium, , ENEA and its linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is...