Published 1996 | Version v1
Report Open

Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4

  • 1. Bettis Atomic Power Lab., West Mifflin, PA (United States)
  • 2. Martin Marietta Corp., Schenectady, NY (United States). Knolls Atomic Power Lab.

Description

Zircaloy-4, which is widely used as a core structural material in Pressurized-Water Reactors (PWR), picks up hydrogen during service. Hydrogen solubility in Zircaloy-4 is low and hydrides precipitate after the Zircaloy-4 matrix becomes supersaturated with hydrogen. These hydrides embrittle the Zircaloy-4. To study hydrogen pickup and concentration, a postirradiation nondestructive radiographic technique for measuring hydrogen concentration was developed and qualified. Experiments on hydrogen pickup were conducted in the Advanced Test Reactor (ATR). Ex-reactor tests were conducted to determine the conditions for which hydrogen would dissolve, migrate, and precipitate. Finally, a phenomenological model for hydrogen diffusion was indexed to the data. This presentation describes the equipment and the model, presents the results of experiments, and compares the model predictions to experimental results

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96011466; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
44 p.
Report number
WAPD-T--3047

Conference

Title
11. international symposium on zirconium in the nuclear industry.
Dates
11-14 Sep 1995.
Place
Garmisch-Partenkirchen (Germany).

Optional Information

Contract/Grant/Project number
Contract AC11-93PN38195
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-950926--1.