Author: L. J. DefferdingPublisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Author: L. J. DefferdingPublisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Scientific and Technical Aerospace Reports
Author: Nuclear Science Abstracts
Author: Atomic Energy Research Reports for Sale by the U.S. Department of Commerce, Office of Technical Services
Author: Business and Defense Services AdministrationPublisher:
ISBN:
Category :
Languages : en
Pages : 68
Book Description
Zirconium in the Nuclear Industry
Author: Gerry D. MoanPublisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
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 2001. 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. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Reactor Materials
Author: Catalog of Technical Reports
Author: United States. Dept. of Commerce. Office of Technical ServicesPublisher:
ISBN:
Category :
Languages : en
Pages : 850
Book Description
Reactor Core Materials
Author: Energy Research Abstracts
Author: Atomindex
Author: International Atomic Energy AgencyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1464
Book Description