Modeling the corrosion of high-level waste containers: CAM-CRM interface
A key component of the Engineered Barrier System (EBS) being designed for containment of spent-fuel and high-level waste at the proposed geological repository at Yucca Mountain, Nevada is a two-layer canister. In this particular design, the inner barrier is made of a corrosion resistant material (CRM) such as Alloy 825, 625 or C-22, while the outer barrier is made of a corrosion-allowance material (CAM) such as A5 16 or Monel 400. At the present time, Alloy C-22 and A516 are favored. This publication addresses the development of models to account for corrosion of Alloy C-22 surfaces exposed directly to the Near Field Environment (NFE), as well as to the exacerbated conditions in the CAM-CRM crevice. [5]. Haynes International has published corrosion rates of Alloys 625 and C-22 in artificial crevice solutions (5-10 wt. % FeCl,) at various temperatures (25, 50 and 75 C) [6,7]. In this case, the observed rates for Alloy C-22 appear to be due to passive dissolution. It is believed that Alloy C-22 must be at an electrochemical potential above the repassivation potential to initiate localized corrosion.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE Office of Defense Programs (DP) (US)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 14695
- Report Number(s):
- UCRL-ID-129120; TRN: US0106216
- Resource Relation:
- Other Information: PBD: 1 Jun 1998
- Country of Publication:
- United States
- Language:
- English
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Modeling the corrosion of high-level waste containers: CAM-CRM interface
MODELING THE CORROSION OF HIGH-LEVEL WASTE CONTAINERS CAM-CRM INTERFACE
Related Subjects
36 MATERIALS SCIENCE
CORROSION RESISTANT ALLOYS
CONTAINERS
CORROSION
DESIGN
DISSOLUTION
YUCCA MOUNTAIN
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE DISPOSAL
HIGH-LEVEL RADIOACTIVE WASTES
SPENT FUELS
INCONEL 625
MONEL 400
HASTELLOYS
STEEL-ASTM-A516