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Published by American Association for Testing and Materials in Philadelphia, PA .
Written in English

Subjects:

  • Nuclear fuel claddings -- Congresses.,
  • Zirconium alloys -- Congresses.,
  • Zircaloy-2 -- Congresses.

Book details:

Edition Notes

StatementC.M. Eucken and A.M. Garde, editors.
SeriesSTP -- 1132., ASTM special technical publication -- 1132.
ContributionsEucken, Craig M., 1951-, Garde, A. M., ASTM Committee B-10 on Reactive and Refractory Metals and Alloys., Japan Society of Newer Metals., Nihon Genshiryoku Gakkai., International Symposium on Zirconium in the Nuclear Industry (9th : 1990 : Kobe, Japan)
Classifications
LC ClassificationsTK9207.5 .Z58 1991
The Physical Object
Paginationxii, 795 p. :
Number of Pages795
ID Numbers
Open LibraryOL18003377M
ISBN 10080311463X

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Zirconium in the Nuclear Industry: Tenth International Symposium (Astm Special Technical Publication) by Anand M. Garde (Author), E. Ross Bradley (Editor)Cited by: Half of the papers in this unique publication relate to corrosion and hydriding behavior, the most important current issues in the industry. A quarter of the papers deal with in-reactor studies. The remaining papers discuss the behavior and properties of zirconium alloys for the intermediate storage of spent fuel. Zirconium in the Nuclear Industry: Ninth International Symposium, Stp (Astm Special Technical Publication) by Craig M. Eucken (Author), A. M. Garde (Editor). Adamson alloys American Society anisotropy annealing ASTM International ASTM STP Atomic Energy autoclave axial basal pole behavior burst calculated Chalk River circumferential cold-worked concentration conium cooling corrosion crack growth creep and growth creep rate D. G. Franklin decrease deformation dependence diameter dislocation density effect experimental fluence flux fuel rod furnace grain boundaries growth rate growth strain hafnium hoop stress hydride hydrogen in-reactor .

Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Publication Zirconium in the Nuclear Industry: 12th International Symposium. 44 papers discuss the history, processing, use, and properties of Zirconium and Publication Zirconium in the Nuclear Industry: 12th International Symposium. 44 papers discuss the history, processing, use, and properties of Zirconium and its alloys. These papers were presented at the 18th International Symposium on Zirconium in the Nuclear Industry, sponsored by ASTM International Committee B10 on Reactive and Refractory Metals and Alloys. It took place May , , in Hilton Head, South Carolina. Th is Compilation of Selected Technical Papers, STP, Zirconium in the Nuclear Industry: 17th International Symposium, contains peer-reviewed papers that were presented at a symposium held February 3–7, in Hyderabad, India. Th e sym-posium was sponsored by ASTM International Committee B10 on Reactive and Re-.

Zirconium in the Nuclear Industry: Tenth International Symposium, Volume 10 ASTM STP Volume of ASTM special technical publication Volume of ASTM special technical publication: American Society for Testing and Materials Volume of ASTM, STP Journal of ASTM International: Selected technical papers, ISSN Volume of. zirconium alloys in the nuclear industry. Since their development in the s and introduction into commercial nuclear power plants in the s, the zirconium-based alloys Zircaloy-2 and -4, Zr-lNb, and ZrNb are the alloys currently used in the world's reactors. ISBN: OCLC Number: Notes: "This STP contains the papers presented at the 16th International Symposium on Zirconium in the Nuclear Industry held in Chengdu, Sichuan Province, China, May , "--Page ix. Half of the papers in STP relate to corrosion and hydriding behavior, the most important current issues in the industry. A quarter of the papers deal with in-reactor studies. The remaining papers discussed the behavior and properties of Zr alloys for .