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Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials

Conference:

Abstract

As shown by recent developments beryllium has become one of the most important materials in the development of fusion reactors. It is practically the only neutron multiplier available for blankets with ceramic breeder materials and can be used with liquid metal breeders as well. It is one of the most likely materials to be used on the surface of the first walls and of the divertor. The neutron irradiation behavior of beryllium in a fusion reactor is not well know. Beryllium was extensively irradiated about 25-40 years ago and has been used since then in material testing reactors as reflector. In the meantime, however, beryllium has been improved quite considerably. Today it is possible to obtain commercially beryllium which is much more isotropic and contains smaller ammounts of oxide. There are already indications that these new kinds of beryllium behave better under irradiation. (orig.)
Authors:
Dalle Donne, M [1] 
  1. ed.
Publication Date:
Dec 01, 1993
Product Type:
Conference
Report Number:
KFK-5271; CONF-9310182-
Reference Number:
SCA: 700450; 700480; 700000; PA: DEN-94:0FN562; EDB-95:018986; SN: 95001306266
Resource Relation:
Conference: Workshop on beryllium for fusion applications,Karlsruhe (Germany),4-5 Oct 1993; Other Information: PBD: Dec 1993
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BERYLLIUM; BREEDING BLANKETS; DIVERTORS; IRRADIATION; PHYSICAL RADIATION EFFECTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR MATERIALS; FIRST WALL; NEUTRON REFLECTORS; SAFETY; WASTE DISPOSAL; 700450; 700480; 700000; BLANKETS AND COOLING SYSTEMS; COMPONENT DEVELOPMENT; MATERIALS STUDIES; PLASMA PHYSICS AND FUSION
OSTI ID:
10106301
Research Organizations:
Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Neutronenphysik und Reaktortechnik; Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Kernfusion; Association Euratom-Kernforschungszentrum Karlsruhe GmbH (KFK) (Germany)
Country of Origin:
Germany
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 0303-4003; Other: ON: DE95726893; TRN: DE94FN562
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
349 p.
Announcement Date:
Jan 21, 1995

Conference:

Citation Formats

Dalle Donne, M. Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials. Germany: N. p., 1993. Web.
Dalle Donne, M. Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials. Germany.
Dalle Donne, M. 1993. "Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials." Germany.
@misc{etde_10106301,
title = {Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials}
author = {Dalle Donne, M}
abstractNote = {As shown by recent developments beryllium has become one of the most important materials in the development of fusion reactors. It is practically the only neutron multiplier available for blankets with ceramic breeder materials and can be used with liquid metal breeders as well. It is one of the most likely materials to be used on the surface of the first walls and of the divertor. The neutron irradiation behavior of beryllium in a fusion reactor is not well know. Beryllium was extensively irradiated about 25-40 years ago and has been used since then in material testing reactors as reflector. In the meantime, however, beryllium has been improved quite considerably. Today it is possible to obtain commercially beryllium which is much more isotropic and contains smaller ammounts of oxide. There are already indications that these new kinds of beryllium behave better under irradiation. (orig.)}
place = {Germany}
year = {1993}
month = {Dec}
}