Published September 1, 2017 | Version v1
Journal article

Functional materials for breeding blankets—status and developments

  • 1. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)
  • 2. Quantum and Radiological Science and Technology, 2-166 Oaza-Obuchi-Aza-Omotedate, Rokkasho-mura, Kamikita-gun, Aomori 039-3212 (Japan)
  • 3. University of California Los Angeles, 43-133 Engineering IV University of California 420 Westwood Plaza Mail Code 159710 Los Angeles, CA 90095-1597 (United States)

Description

The development of tritium breeder, neutron multiplier and flow channel insert materials for the breeding blanket of the DEMO reactor is reviewed. Present emphasis is on the ITER test blanket module (TBM); lithium metatitanate (Li2TiO3) and lithium orthosilicate (Li4SiO4) pebbles have been developed by leading TBM parties. Beryllium pebbles have been selected as the neutron multiplier. Good progress has been made in their fabrication; however, verification of the design by experiments is in the planning stage. Irradiation data are also limited, but the decrease in thermal conductivity of beryllium due to irradiation followed by swelling is a concern. Tests at ITER are regarded as a major milestone. For the DEMO reactor, improvement of the breeder has been attempted to obtain a higher lithium content, and Be12Ti and other beryllide intermetallic compounds that have superior chemical stability have been studied. LiPb eutectic has been considered as a DEMO blanket in the liquid breeder option and is used as a coolant to achieve a higher outlet temperature; a SiC flow channel insert is used to prevent magnetohydrodynamic pressure drop and corrosion. A significant technical gap between ITER TBM and DEMO is recognized, and the world fusion community is working on ITER TBM and DEMO blanket development in parallel. (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/1741-4326/aa7e4e

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
57
Journal Issue
9
Journal Page Range
[19 p.]
ISSN
0029-5515
CODEN
NUFUAU