Basic Studies in the Field of High-Temperature Engineering

Author/creator NEA Staff
Other author Organisation for Economic Co-operation and Development.
Format Electronic
Publication InfoWashington : Organization for Economic Cooperation & Development
Description360 p. ill 27.000 x 020.000 cm.
Supplemental ContentFull text available from OECD Global
Subjects

SeriesNuclear Science Ser.
Summary Annotation These proceedings of an October 2001 meeting provide an overview of research on the improvement of material properties for high- temperature, gas-cooled reactor (HTGR) applications, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance. Specific topics include improvement in ductility of refractory metals by neutron irradiation, development of in-core test capabilities for material characterization, advanced graphite oxidation models, evidence of dramatic fission product release from irradiated nuclear ceramics, and an analysis of irradiation creep in nuclear graphites. There is no subject index. Annotation copyrighted by Book News, Inc., Portland, OR
Access restrictionAvailable only to authorized users.
Technical detailsMode of access: World Wide Web
Genre/formElectronic books.
LCCN 2002494267
ISBN9789264197961
ISBN9264197966 (Trade Paper) Active Record
Standard identifier# 9789264197961
Stock number66 2002 10 1 P 1 00019989

Availability

Library Location Call Number Status Item Actions
Electronic Resources Access Content Online ✔ Available