ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials [electronic resource].
- Washington, D.C : United States. Dept. of Energy. Office of Energy Research, 1989.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: (10 pages) : digital, PDF file
- Additional Creators:
- Argonne National Laboratory
United States. Department of Energy. Office of Energy Research
United States. Department of Energy. Office of Scientific and Technical Information
- The International Thermonuclear Experimental Reactor (ITER) activity includes specific R D in critical areas to support the ITER design. Several of the critical tasks defined as part of the ITER validating R D are materials related. This paper presents a summary of the breeder/blanket materials related R D conducted by the four participating parties; viz., European Community, Japan, Soviet Union and the United States. The current effort includes several subtasks in each of the following four task areas: ceramic breeder materials; lead-lithium breeder; aqueous salt solutions; and neutron multiplier materials. The objective and scope of each subtask is states. Although this work was initiated in late 1988, important results have been obtained in all four areas. The work on ceramic breeders includes properties measurements, compatibility studies, and tritium recovery experiments with Li₂O and selected ternary ceramics. Investigations on the lead-lithium breeder have focused primarily on properties, compatibility, and tritium extraction from the 17Li-83Pb eutectic alloy. The work on the aqueous salt breeders includes corrosion, solution chemistry, and radiolysis effects in a radiation environment. Investigations defined under the neutron multiplier task are focused on beryllium; however, lead in the lithium lead alloy also serves as a neutron multiplier. The schedule and planned future work in each area are summarized. 1 refs., 6 tabs.
- Published through SciTech Connect.
4. international conference on fusion reactor materials, Kyoto (Japan), 4-8 Dec 1989.
Smith, D.L.; Yoshida, H. . Tritium Process Lab.; Daenner, W. . NET Design Team; Kalinin, G.
- Funding Information:
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