Basic Studies in the Field of High-temperature Engineering: Second Information Exchange Meeting, Paris, France, 10-12 October 2001, Volume 638
Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2002 - Business & Economics - 356 pages
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
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J Kendall M Methnani
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Nuclear Science Basic Studies in the Field of High-temperature Engineering ...
OECD,Nuclear Energy Agency
No preview available - 2002
activities analysis annealing Atomic behaviour BNFL burn-off burn-up calculations ceramic components control rod coolant core crack creep strain creeping wave decay heat decay heat removal direct cycle dose effect embrittlement experimental fast neutron fission products fluence FRAMATOME Framework Programme fuel elements fuel particles Graphite Database helium High-temperature Engineering high-temperature gas-cooled reactors High-temperature Reactor HTGR HTR fuel HTR-M HTTR IAEA in-core in-pile increase ion irradiation IPyC irradiation creep irradiation temperature irradiation test irradiation-induced JAERI Japan JMTR load Magnox materials measured mechanical microstructure neutron irradiation nuclear graphite operation optical fibre organisations oxidation PBMR pebble bed performed Petten pore prediction presented pressure properties radiation radiation hardening reactivity release safety samples shown in Figure specimens stress structural superplastic deformation surface tensile test reactor thermal tritium turbine UK Creep Law vessel Young's modulus