journal article·2011-10Open access

Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor

T. Hino, H. Shibata, Y. Yamauchi, Y. Nobuta, S. Suzuki, M. Akiba

Journal of Nuclear Materials· Volume 417· Issue 1-3

Abstract

The tritium produced in a tritium breeder of blanket has to be recovered under the temperature distribution to reduce the tritium inventory. Lithium titanate pebbles were irradiated by deuterium ions with different temperatures and ion fluences. The deuterium retained in the pebbles desorbed in forms of HD, D2, HDO and D2O. The amount of retained deuterium decreased for the temperature higher than 473 K, and became to zero for the temperature higher than 773 K. If the temperature range is taken from 573 to 1173 K in the solid breeder TBM, the tritium inventory is lower than 1 gram. However, in the demonstration reactor, the total tritium inventory of blankets becomes a few kilograms. For the reduction of the tritium inventory, the region with the low temperature region has to be significantly reduced.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Muon and positron interactions and applications

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References (11)

Show source-provided references
1. Ying · J. Nucl. Mater. · 2007 · 367–370 · 128110.1016/j.jnucmat.2007.03.240 ↗
2. Kinjyo · Fusion Sci. Technol. · 2005 · 48 · 46
3. Baba · Fusion Eng. Des. · 2000 · 49–50 · 48310.1016/S0920-3796(00)00255-6 ↗
4. Kawamura · J. Nucl. Mater. · 1994 · 218 · 7
5. Japan Atomic Energy Agency Report, JAERI-Review 2005-011, 2005.
6. Roux · J. Nucl. Mater. · 1996 · 233–237 · 143110.1016/S0022-3115(96)00136-5 ↗
7. Tanaka · J. Plasma Fusion Res. · 2005 · 81 · 43410.1585/jspf.81.434 ↗
8. Hino · Fusion Eng. Des. · 2008 · 83 · 117310.1016/j.fusengdes.2008.07.007 ↗
9. Tsuchiya · J. Nucl. Mater. · 2002 · 307–311 · 81710.1016/S0022-3115(02)01304-1 ↗
10. M. Enoeda, Development of blanket materials in JAEA, 2nd Roadmap Meeting for Development of Fusion Reactor, Fusion Forum in Japan, Tokyo, 2006.
11. T. Hino, H. Shibata, Y. Yamauchi, M. Akiba, Deuterium retention and desorption behavior of lithium titanate, Advanced Blanket Meeting at National Institute of Fusion Science (NIFS), July 1, 2008.