Localized corrosion and stress corrosion cracking of candidate materials for high-level radioactive waste disposal containers in U.S.; A critical literature review
- Lawrence Livermore National Lab., CA (USA)
Three ion-based to nickel-based austenitic alloys and three copper-based alloys are being considered in the United States as candidate materials for the fabrication of high-level radioactive waste containers. The austenitic alloys are Types 304L and 316L stainless steels as well as the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper) CDA 613 (Cu7Al), and CDA 715 (Cu-30Ni). Waste in the forms of spent fuel assemblies from reactors and borosilicate glass will be sent to a proposed repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and in gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to a lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys.
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 137636
- Report Number(s):
- CONF-881066-; ISBN 0-931837-97-9; TRN: 90:005872
- Resource Relation:
- Conference: 12. international symposium on the scientific basis for nuclear waste management, Berlin (Germany), 10-13 Oct 1988; Other Information: PBD: 1989; Related Information: Is Part Of Scientific basis for nuclear waste management XII; Lutz, W. [Hahn-Meitner-Institut Berlin G.m.b.H. (Germany, F.R.)]; Ewing, R.C. [New Mexico Univ., Albuquerque, NM (USA)]; PB: 1001 p.; Materials Research Society symposium proceedings. Volume 127
- Country of Publication:
- United States
- Language:
- English
Similar Records
Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers
Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers; Overview
Related Subjects
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
36 MATERIALS SCIENCE
CONTAINERS
STRESS CORROSION
HIGH-LEVEL RADIOACTIVE WASTES
NICKEL BASE ALLOYS
CRACKING
IRON BASE ALLOYS
SPENT FUEL CASKS
MATERIALS TESTING
USA
STAINLESS STEELS
COPPER BASE ALLOYS
CREVICE CORROSION
CORROSION RESISTANCE
Yucca Mountain Project