US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities

Conference · Mon Aug 01 00:00:00 EDT 1988

OSTI ID:6758680

Baker, C C

This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/. 1 ref., 2 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6758680
• Report Number(s): CONF-881031-16; ON: DE89000540
• Resource Relation: Conference: 8. topical meeting on technology of fusion energy, Salt Lake City, UT, USA, 9 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
GAS BLANKETS
SHIELDING
TOKAMAK TYPE REACTORS
BERYLLIUM
HELIUM
SAFETY
TRITIUM
ALKALINE EARTH METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
ELEMENTS
FLUIDS
GASES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
METALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering