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Title: An outboard shield design for TIBER-II with potential for tritium self-sufficiency: Appendix A-1

The outboard breeding shield design for TIBER-II is described. The design allows for tritium self-sufficiency without compromising magnet protection, design simplicity, and the testing mission of the device. The shield consists of a beryllium pebble front zone backed by a steel pebble zone. The shield is cooled by an aqueous solution containing 16 g LiNO/sub 3/ per 100 cm/sup 3/. A double first wall is used to insure uniform cooling and minimize pressure. The design pressure for the outboard shield is 0.19 MPa and the coolant temperature is less than 75/sup 0/C. 6 refs., 5 figs., 3 tabs.
Authors:
;
Publication Date:
OSTI Identifier:
5757365
Report Number(s):
CONF-871007-49
ON: DE88002459
DOE Contract Number:
FG02-87ER52140
Resource Type:
Conference
Resource Relation:
Conference: 12. symposium on fusion engineering, Monterey, CA, USA, 12 Oct 1987; Other Information: Paper copy only, copy does not permit microfiche production
Research Org:
Wisconsin Univ., Madison (USA). Fusion Technology Inst.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; SHIELDING MATERIALS; DESIGN; TIBER-X TOKAMAK; BERYLLIUM; BREEDING BLANKETS; DIVERTORS; FIRST WALL; GRAPHITE; HYDRAULICS; LITHIUM COMPOUNDS; THERMAL ANALYSIS; TRITIUM; ALKALI METAL COMPOUNDS; ALKALINE EARTH METALS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON; ELEMENTAL MINERALS; ELEMENTS; FLUID MECHANICS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATERIALS; MECHANICS; METALS; MINERALS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES 700201* -- Fusion Power Plant Technology-- Blanket Engineering; 700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing