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

Patent · Mon Jan 01 00:00:00 EST 1990

OSTI ID:867334

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

---

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 (United States)
• 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

Related Subjects

method
predict
relative
hydriding
zirconium
alloys
nuclear
irradiation
out-of-reactor
screening
in-reactor
behavior
zirconium-bsed
materials
disclosed
samples
zirconium-based
composition
fabrication
autoclaved
relatively
concentrated
0m
aqueous
lithium
hydroxide
solution
constant
temperatures
water
reactor
coolant
temperature
range
280
degree
316
tested
procedure
compared
basis
ratio
hydrogen
weight
oxide
accurately
rate
hyriding
subject
irradiated
corrision
lithium hydroxide
coolant temperature
constant temperature
water reactor
zirconium alloy
reactor coolant
temperature range
zirconium alloys
hydroxide solution
reactor method
accurately predict
oxide solution
predict relative
/436/73/376/