Published 1991 | Version v1
Book

Lithium uptake and the corrosion of zirconium alloys in aqueous lithium hydroxide solutions

  • 1. AECL Research, System Chemistry and Corrosion Branch, Chalk River Lab., Chalk River, Ontario (Canada)

Description

This paper reports on corrosion films on zirconium alloys that were analyzed for lithium by Atomic Absorption Spectroscopy (AAS), Secondary Ion Mass Spectrometry (SIMS), and Infrared Reflection Absorption Spectroscopy (IRAS). The oxides grown in reactor in dilute lithium hydroxide solution, specimens cut from Zircaloy, and Zr-2.5Nb alloy pressure tubes removed from CANDU (Canada Deuterium Uranium, Registered Trademark) reactors showed low concentrations of lithium (4 to 50 ppm). The lithium was not leachable in a warm dilute acid. 6Li undergoes transmutation by the 6Li(n,t)4He reaction. However, SIMS profiles for d 7Li were identical through the bulk oxide and the isotopic ratio was close to the natural abundance value. The lithium in the oxide, existing as adsorbed lithium on the surface, has been in dynamic equilibrium with lithium in the coolant, and, in spite of many Effective Full Power Years (EFPY) of operation, lithium added to the CANDU coolant at ∼2.5 ppm is not concentrating in the oxides. On the other hand, corrosion films grown in the laboratory in concentrated lithium hydroxide solutions were very porous and contained hundreds of ppm of lithium in the oxide

Additional details

Publishing Information

Publisher
ASTM.
Imprint Place
Philadelphia, PA (United States)
ISBN
0-8031-1463X
Imprint Title
Zirconium in the nuclear industry
Imprint Pagination
795 p.
Journal Page Range
p. 613-627.

Conference

Title
9. American Society for Testing and Materials (ASTM) international symposium on zirconium in the nuclear industry.
Dates
5-8 Nov 1990.
Place
Kobe (Japan).

Optional Information

Secondary number(s)
CONF-901107--.