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STP 939


Zirconium in the Nuclear Industry


Editor(s): Adamson; Van Swan

Pages: 816

Published: 1987

Soft Cover

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Forty papers deal with properties of Zircaloy and to a lesser extent, Zr-2.5-Nb. The majority covers fabrication and physical properties, general corrosion and hydriding, fracture and fatigue, and stress corrosion cracking. Special consideration is given to irradiation growth, Zircaloy cladding behavior under conditions expected in a loss-of-coolant accident, and nodular corrosion.

Zirconium in the Nuclear Industry
ISBN13: 978-0-8031-0935-3
STOCK# STP939

STP939-C01   STP939-C02   STP939-C03   STP939-C04   STP939-C05   STP939-C06   STP939-C07   STP939-F01   STP939-F02   STP939-R01   STP939-R02   STP939-R03   STP939-SN   STP 939   STP939   STP939   STP939   STP 939