Beryllium processing technology review for applications in plasma-facing components

Technical Report · Thu Jul 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10176907· OSTI ID:10176907

Castro, R G; Jacobson, L A; Stanek, P W

Materials research and development activities for the International Thermonuclear Experimental Reactor (ITER), i.e., the next generation fusion reactor, are investigating beryllium as the first-wall containment material for the reactor. Important in the selection of beryllium is the ability to process, fabricate and repair beryllium first-wall components using existing technologies. Two issues that will need to be addressed during the engineering design activity will be the bonding of beryllium tiles in high-heat-flux areas of the reactor, and the in situ repair of damaged beryllium tiles. The following review summarizes the current technology associated with welding and joining of beryllium to itself and other materials, and the state-of-the-art in plasma-spray technology as an in situ repair technique for damaged beryllium tiles. In addition, a review of the current status of beryllium technology in the former Soviet Union is also included.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 10176907
• Report Number(s): LA-12545-MS; ON: DE93018396; TRN: AHC29308%%33
• Resource Relation: Other Information: PBD: Jul 1993
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
36 MATERIALS SCIENCE
ITER TOKAMAK
THERMONUCLEAR REACTOR MATERIALS
BERYLLIUM
JOINING
PLASMA ARC SPRAYING
TECHNOLOGY ASSESSMENT
FIRST WALL
FABRICATION
REPAIR
USSR
RESEARCH PROGRAMS
HEAT TREATMENTS
POROSITY
BRAZING
700480
360101
COMPONENT DEVELOPMENT
MATERIALS STUDIES
PREPARATION AND FABRICATION