ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials

Conference · Fri Dec 01 00:00:00 EST 1989

OSTI ID:7252447

Smith, D L ^[1]; Daenner, W ^[2]; Kalinin, G ^[3]; Yoshida, H ^[4]

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1. Argonne National Lab., IL (USA)
2. Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.). NET Design Team
3. Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki, Moscow (USSR)
4. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tritium Process Lab.

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 Li{sub 2}O 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.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7252447
• Report Number(s): CONF-891204-21; ON: DE90007807; TRN: 90-008232
• Resource Relation: Conference: 4. international conference on fusion reactor materials, Kyoto (Japan), 4-8 Dec 1989
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
AQUEOUS SOLUTIONS
CERAMICS
ITER TOKAMAK
LITHIUM BASE ALLOYS
SALTS
THERMONUCLEAR REACTOR MATERIALS
ALLOYS
CLOSED PLASMA DEVICES
DISPERSIONS
LITHIUM ALLOYS
MATERIALS
MIXTURES
REACTOR COMPONENTS
SOLUTIONS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing