Corrosion studies on POLLUX cask material
Creators
- 1. Deutsche Gesellschaft fur Wiederaufarbeitung von Kernbrennstoffen mbH, Hannover (Germany, F.R.)
Description
Within the POLLUX engineering concept, the material concept for safe containment of radioactive materials includes corrosion resistance, reproducible quality, material reliability, and controlled component quality. These requirements with regard to material and applied technology are optimally satisfied within the POLLUX concept, where the selected steel grade, 15 MnNi 6.3, for the cask body and plasma hot-wire surfacing (PHS) combine a base material with a proven surfacing welding process. Metallographic examinations of Inconel and Hastelloy C4 layers have been performed for characterizing the structure and determining the thickness of the applied layers. Microprobe analyses are conducted for examining the layered structure achieved with the transition zones between the layers, as well as for confirming the attainment of Hastelloy quality in the uppermost layer. The Hastelloy C4 specimens employed for the corrosion tests were surface-welded and originated from the topmost layer of the cladding surfaced with the use of the PHS process. MgCl2 was used in most of the studies as the corrosive media. It was concluded that the microstructure and purity of the weld layer is important in regard to corrosion resistance; and that higher temperatures in the corrosive media influence resistance
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Joint United States/Federal Republic of Germany Technical Exchange Conferences on Nuclear Waste
- Imprint Pagination
- 481 p.
- Journal Page Range
- p. 7, Paper C3.
- Report number
- BMI/ONWI/C--290
Conference
- Title
- Joint United States/Federal Republic of Germany technical exchange conference on nuclear package.
- Dates
- 8-11 Mar 1988.
- Place
- Albuquerque, NM (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21037066
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-NI76CR15FE8; BRINES; CASKS; CERAMICS; CLADDING; CORROSION; GEOLOGIC FORMATIONS; HASTELLOYS; HEAT AFFECTED ZONE; MATERIALS TESTING; METALLOGRAPHY; MICROANALYSIS; PLASMA ARC SPRAYING; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTES; RESEARCH PROGRAMS; STRUCTURAL MODELS; TESTING; WELDING
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CONTAINERS; CORROSION RESISTANT ALLOYS; DEPOSITION; FABRICATION; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINING; MANAGEMENT; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; RADIOACTIVE MATERIALS; SPRAY COATING; SURFACE COATING; TITANIUM ADDITIONS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Secondary number(s)
- CONF-880377--.