Parametric study of an autoclave test for nodular corrosion
Description
The use of a steam corrosion autoclave test as a quality control tool for Zircaloy products has been practiced for many years. The most common form of the test is exposure to steam at 672k, 10.3 Mpa (7500F, 1500 psi) for three days. Some years ago it was found that this test did not predict susceptibility to the occurrence nodular corrosion in boiling water reactors (BWR). A number of investigators found that a test at 723 to 773 K would produce nodular corrosion on Zircaloy products and therefore used the test as an index for research work on Zircaloy materials. More recently the test has been proposed as a quality control test on each lot of material. This study of test parameters and interlaboratory variability was undertaken as a necessary part of establishing an ASTM standard for such a test. Temperature of the test was found to be the most significant variable studied, and interlaboratory variation was relatively high when compared with the common 672 K test
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-0935-0
- Imprint Title
- Zirconium in the nuclear industry
- Journal Page Range
- p. 243-254.
Conference
- Title
- 7. international conference on zirconium in the nuclear industry.
- Dates
- 24-27 Jun 1985.
- Place
- Strasbourg (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19075837
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CORROSION; CORROSION PROTECTION; CORROSION RESISTANCE; DESTRUCTIVE TESTING; EXPERIMENT PLANNING; HIGH PRESSURE; HIGH TEMPERATURE; SPECIFICATIONS; STEAM; ZIRCALOY; ZIRCONIUM; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; MATERIALS TESTING; METALS; PLANNING; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM BASE ALLOYS