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

Abstract

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 schedulemore » and planned future work in each area are summarized. 1 refs., 6 tabs.« less

Authors:
 [1];  [2];  [3];  [4]
  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.
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
Sponsoring Org.:
DOE/ER
OSTI Identifier:
7252447
Report Number(s):
CONF-891204-21
ON: DE90007807; TRN: 90-008232
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: 4. international conference on fusion reactor materials, Kyoto (Japan), 4-8 Dec 1989
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Smith, D L, Daenner, W, Kalinin, G, and Yoshida, H. ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials. United States: N. p., 1989. Web.
Smith, D L, Daenner, W, Kalinin, G, & Yoshida, H. ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials. United States.
Smith, D L, Daenner, W, Kalinin, G, and Yoshida, H. Fri . "ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials". United States. https://www.osti.gov/servlets/purl/7252447.
@article{osti_7252447,
title = {ITER (International Thermonuclear Experimental Reactor) R and D breeder blanket materials},
author = {Smith, D L and Daenner, W and Kalinin, G and Yoshida, H},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1989},
month = {12}
}

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