Nuclear Science Basic Studies in the Field of High-Temperature Engineering: Second Information Exchange Meeting: Paris, France 10-12 October 2001 - Tapa blanda
Sinopsis
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 c. Book News, Inc., Portland, OR (booknews.com)
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Reseña del editor
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 c. Book News, Inc., Portland, OR (booknews.com)
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