ASTM STP 1132 Zirconium in the Nuclear Industry: Ninth International Symposium
ASTM STP 1132 is offered by IHS as part of an online subscription to the Special Technical Publications Library.
You may also purchase this publication alone from the IHS Standards Store.
Euken, CM
ASTM Committee B-10 on Reactive and Refractory Metals and Alloys in cooperation with the Japan Society of Newer Metals and the Japan Atomic Energy Society sponsored the Ninth International Symposium on Zirconium in the Nuclear Industry. The symposium was held in November, 1990. This publication contains the proceedings from the symposium.
The proceedings begin with an invited paper that reviews the primary findings of a workshop on zirconium-alloy corrosion arranged by the International Atomic Energy Agency (IAEA), in cooperation with the U.S. Department of Energy (DOE). The paper’s author considers some previously reported work to provide perspective on the issue of in-reactor oxidation of zirconium alloys present in almost all water-cooled and water-moderated reactors and summarizes the state of the technology. The balance of papers presented in the publication are organized under the headings
- Fabrication
- Mechanical Properties
- Corrosion: Effects of Processing and Alloying
- Corrosion: Mechanisms
- Corrosion: Modeling and Lithium Effects
- Corrosion: In-Reactor
Specific topics covered by the papers in this extensive reference - more than 750 pages and 36 papers - include:
- deformability
- zirconium lined cladding tube
- hot working characteristics of zircaloy-2
- statistical models of manufacturing parameters
- texture control
- fracture toughness Evaluation
- heat-treated Zr-2.5Nb pressure tubes
- tensile deformation
- crystallographic texture
- zircaloy sheet
- microstructure
- mechanical properties
- Zr-Sn alloys
- oxidation
- growth in sircaly-4 fuel clad
- neutron irradiation
- creep
- pressure tube deformation
- CANDU reactors
- controlled composition
- uniform corrosion resistance
- nodular corrosion resistance
- highly corrosion resistant zirconium base alloys
- Raman spectroscopy
- overall oxygen diffusion
- photo-electrochemical characteristics
- zirconium oxide films
- oxide-metal interface
- uniformly corroded zircaloy
- evaluation in-reactor corrosion performance
- out-of-pile loop performance
- aqueous corrosion
- hydride precipitation
- lithium uptake
- aqueous lithium hydroxide solutions
- pressurized water reactor (PWR)
- lithiated water environments
- borated water environments
- effects of LiOH
- variables that influence corrosion
- amorphization of precipitates in zircaloy
- charged particle irradiation
Purchase this STP as a reference if you are an engineer or researcher concerned about zirconium corrosion and reactor life.