ASTM STP 1423 Zirconium in the Nuclear Industry: Thirteenth International Symposium
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Moan GD
This STP, Zirconium in the Nuclear Industry: Thirteenth International Symposium, contains papers presented at the symposium with the same name sponsored by ASTM Committee B-10 on Reactive and Refractory Metals and Alloys held in June, 2001. Presenters and attendees at the symposium were involved and interested in the production and use of Zr alloys, their properties and behavior during nuclear service, the design of Zr components, and their testing after service.
More than 40 papers from the symposium are contained in this STP. Corrosion and hydriding behavior were highlighted as the most important current issues, and about one half of the papers were related to them. In-reactor studies formed the basis for about one quarter of the papers. Also, two papers were related to the behavior and properties of Zr alloys for the intermediate storage of spent fuel. Other papers covered basic metallurgy, including studies of second phase particles, irradiation creep and growth, material performance during a loss of coolant accident (LOCA), and reactivity initiated accidents (RIAs).
Specific topics covered by papers in this collection include:
- in-reactor corrosion
- BWR
- shadow corrosion
- second-phase particles (SPP)
- irradiation Resistant Precipitates
- chemical states of tin and iron atoms in zirconium alloy oxide film
- Mössbauer spectroscopy
- Zircaloy-4
- corrosion resistance
- role of lithium and boron on the corrosion of Zircaloy-4
- water oxidation
- PWR
- transformation of the oxide layer (ZrO)
- electrochemical studies
- lithiated water
- deuterium pickup
- lattice coherency
- interplanar spacing
- Zr-2.5Nb alloy microstructure
- delayed hydride cracking
- activated slip systems
- alpha-annealed Zircaloy-4
- Zr1%Nb alloy cladding tubes
- calandria tubes
- CANDU reactor
- dilute Zr alloys
- in-situ clad straining
- synchrotron radiation
- LWR
- highly irradiated BWR LTP cladding
This STP provides critical information of interest to engineers, scientists, and researchers working in nuclear power and particularly those involved in the testing, development, and specification of materials for use in nuclear reactor design and operations.