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

Patent · Tue Apr 10 00:00:00 EDT 1990

OSTI ID:7167792

Johnson, Jr, A B; Levy, I S; Trimble, D J; Lanning, D D; Gerber, F S

An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-based materials is disclosed. Samples of zirconium-based materials having different compositions and/or fabrication methods 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 to 316 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 hydriding for the same materials when subject to in-reactor (irradiated) corrosion. 1 figure.

• DOE Contract Number: AC06-76RL01830
• Assignee: Battelle Memorial Inst., Richland, WA (United States)
• Patent Number(s): A; US 4916076
• Application Number: PPN: US 7-208332
• OSTI ID: 7167792
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHEMICAL REACTIONS
EMBRITTLEMENT
FORECASTING
HYDRIDATION
HYDROGEN EMBRITTLEMENT
MATERIALS
MATERIALS TESTING
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
TESTING
WATER COOLED REACTORS
ZIRCONIUM ALLOYS