A laboratory method to predict hydriding properties of zirconium alloys under irradiation
A corrosion and hydriding test series on zirconium alloys in the Engineering Test Reactor G-7 loop demonstrated relatively large lot-to-lot and alloy-to-alloy differences in hydriding rates under irradiation. Similar differences were also found among irradiated Zircaloy-2 pressure tubes fabricated by three suppliers for the Hanford Site N Reactor. This substantial in-reactor hydriding data base and access to archive materials from these alloys permitted an investigation of methods to reproduce the in-reactor hydriding orders-of-merit by an out-of-reactor method. The out-of-reactor method selected for investigation consisted of autoclaving alloys in relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solutions. The test times ranged from 7 to 35 d, and the samples were held at constant temperatures within the water reactor coolant temperature range (280/degree/C to 315/degree/C). The in-reactor hydriding behavior for several lots of Zircaloy-2, one lot of Zircaloy-4, and one lot of Zr--2.5Nb was reproduced in the lithium hydroxide tests. The hydriding rates were compared on the basis of the ratio of hydrogen weight gain to oxide weight gain. 13 refs., 4 figs., 6 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 7065498
- Report Number(s):
- WHC-SA-0289; CONF-880696-2; ON: DE89001916
- Resource Relation:
- Conference: 8. international conference on zirconium in the nuclear industry, San Diego, CA, USA, 18 Jun 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ZIRCALOY 2
HYDRIDATION
ZIRCALOY 4
ZIRCONIUM ALLOYS
AUTOCLAVES
CORRELATIONS
CORROSION
LITHIUM HYDROXIDES
N-REACTOR
WATER COOLED REACTORS
ALKALI METAL COMPOUNDS
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
HYDROGEN COMPOUNDS
HYDROXIDES
IRON ADDITIONS
IRON ALLOYS
LITHIUM COMPOUNDS
LWGR TYPE REACTORS
OXYGEN COMPOUNDS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTORS
TIN ALLOYS
ZIRCALOY
ZIRCONIUM BASE ALLOYS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors