Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation

Patent · Sun Dec 31 23:00:00 EST 1989

OSTI ID:867334

Levy, Ira S ^[1]; Trimble, Dennis J ^[1]; Lanning, Donald D ^[1]; Gerber, Franna S ^[2]

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1. Kennewick, WA
2. Richland, WA

An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-bsed materials is disclosed. Samples of zirconium-based materials having different composition and/or fabrication are autoclaved in a relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solution at constant temperatures within the water reactor coolant temperature range (280.degree. to 316.degree. C.). Samples tested by this out-of-reactor procedure, when compared on the basis of the ratio of hydrogen weight gain to oxide weight gain, accurately predict the relative rate of hyriding for the same materials when subject to in-reactor (irradiated) corrision.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA
• DOE Contract Number: AC06-76RL01830
• Assignee: Battelle Memorial Institute (Richland, WA)
• Patent Number(s): US 4916076
• OSTI ID: 867334
• Country of Publication: United States
• Language: English

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