Status of beryllium development for fusion applications

Conference · Sun May 01 00:00:00 EDT 1994

OSTI ID:10158197

Billone, M C ^[1]; Donne, M D ^[2]; Macaulay-Newcombe, R G ^[3]

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1. Argonne National Lab., IL (United States)
2. Kernforschungszentrum Karlsruhe GmbH (Germany). Institut fuer Neutronphysik and Reaktortechnik
3. McMaster Univ., Ontario, CA (United States). Dept. of Engineering Physics

Beryllium is a leading candidate material for the neutron multiplier of tritium breeding blankets and the plasma facing component of first wall and divertor systems. Depending on the application, the fabrication methods proposed include hot-pressing, hot-isostatic-pressing, cold isostatic pressing/sintering, rotary electrode processing and plasma spraying. Product forms include blocks, tubes, pebbles, tiles and coatings. While, in general, beryllium is not a leading structural material candidate, its mechanical performance, as well its performance with regard to sputtering, heat transport, tritium retention/release, helium-induced swelling and chemical compatibility, is an important consideration in first-wall/blanket design. Differential expansion within the beryllium causes internal stresses which may result in cracking, thereby affecting the heat transport and barrier performance of the material. Overall deformation can result in loading of neighboring structural material. Thus, in assessing the performance of beryllium for fusion applications, it is important to have a good database in all of these performance areas, as well as a set of properties correlations and models for the purpose of interpolation/extrapolation.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10158197
• Report Number(s): ANL/TD/CP-82439; CONF-940664-8; ON: DE94013424; TRN: 94:012188
• Resource Relation: Conference: ISFNT-3: international symposium on fusion nuclear technology,Los Angeles, CA (United States),27 Jun - 1 Jul 1994; Other Information: PBD: May 1994
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
36 MATERIALS SCIENCE
THERMONUCLEAR REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
BERYLLIUM
MECHANICAL PROPERTIES
BREEDING BLANKETS
FIRST WALL
DIVERTORS
SWELLING
INTERSTITIAL HELIUM GENERATION
TRITIUM RECOVERY
700420
700480
360106
PLASMA-FACING COMPONENTS
COMPONENT DEVELOPMENT
MATERIALS STUDIES
RADIATION EFFECTS