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Kikuchi, Mitsuru; Seki, Yasushi; K. Nakagawa*

Fusion Engineering and Design, 48(3-4), p.265 - 270, 2000/09

 Times Cited Count:18 Percentile:24.45(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Evaluation of strength and pressure integrity for fusion blanket structure

Tanigawa, Hisashi; Gwon, H.; Hirose, Takanori; Nakajima, Motoki; Kawamura, Yoshinori

no journal, , 

Blanket in fusion nuclear reactor has three functions such as neutron shielding, heat recovery and tritium breeding. Blankets with ceramic breeder materials has a box structure made of reduced activation ferritic/martensitic steel, and pebbles of breeder and neutron multiplier materials are packed into the box. Heat and neutron loads on the blanket are cooled by high temperature and pressure coolant such as water and helium. In this study, strength and pressure integrity are assessed for the water-cooled ceramic breeder blanket developed in JAEA. Existing design standards for pressure equipment are used in the analysis and their applicability to the fusion blanket is discussed.

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