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.Files
27063070.pdf
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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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27063070
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DIFFUSION; DISSOLUTION; EXPERIMENTAL DATA; HYDROGEN EMBRITTLEMENT; MATHEMATICAL MODELS; NONDESTRUCTIVE TESTING; POST-IRRADIATION EXAMINATION; PWR TYPE REACTORS; REACTOR MATERIALS; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; DATA; EMBRITTLEMENT; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INFORMATION; IRON ADDITIONS; MATERIALS; MATERIALS TESTING; NUMERICAL DATA; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Contract/Grant/Project number
- Contract AC11-93PN38195
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-950926--1.