Corrosion testing of selected packaging materials for disposal of high-level waste glass in rock-salt formations
Creators
- 1. Kernforschungszentrum Karlsruhe GmbH (Germany)
Description
In previous corrosion studies performed in salt brines, unalloyed steels, Ti 99.8-Pd and Hastelloy C4 have proved to be the most promising materials for long-term resistant packagings to be used in heat-generating waste (vitrified HLW, spent fuel) disposal in rock-salt formations. Investigations of the iron-base materials Ni-Resist D2 and D4, cast iron and Si-cast iron have also been carried out in order to complete the results available to date. The three steels (fine-grained steel, low-carbon steel, cast steel) investigated and Ti 99.8-Pd resisted pitting and crevice corrosion as well as stress-corrosion cracking under all test conditions. Gamma dose-rates of 1 Gy/h - 100 Gy/h or H2S concentrations in the brines as well as welding and explosion plating did not influence noticeably the corrosion behaviour of the materials. Furthermore, the determined corrosion rates of the steels (50 μm/a-250 μm/a, depending on the test conditions) are intercomparable and imply technically acceptable corrosion allowances for the thick-walled containers discussed. For Ti 99.8-Pd no detectable corrosion was observed. By contrast, Hastelloy C4 proved susceptible to pitting and crevice corrosion at gamme dose-rates higher than 1 Gy/h and in the presence of H2S (25 mg/l) in Q-brine. The materials Ni Resist D2 and D4, cast iron and Si-cast iron corroded at negligible rates in the in-situ experiments performed in rock salt/limited amounts of NaCI-brine. Nevertheless, these materials must be ruled out as container materials because they have proved to be susceptible to pitting and intergranular corrosion in previous laboratory studies conducted with MgCI2-rich brine (Q-brine) in excess. 15 refs.; 29 figs.; 7 tabs
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Subtitle (English)
- Task 3. Characterization of radioactive waste forms. A series of final reports (1985-89) No 27
Publishing Information
- Imprint Pagination
- 57 p.
- Report number
- EUR--13672
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 23054706
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Descriptors DEI
- ALLOY-NI62CR16MO15FE3; ALLOY-TI99; ASSE SALT MINE; BRINES; CARBON STEELS; CAST IRON; CHROMIUM-NICKEL STEELS; CORROSION; HIGH-LEVEL RADIOACTIVE WASTES; PACKAGING; RADIOACTIVE WASTE DISPOSAL; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; BORON ADDITIONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COBALT ADDITIONS; CORROSION RESISTANT ALLOYS; HASTELLOYS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MANAGEMENT; MATERIALS; MINES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTES; SILICON ALLOYS; STAINLESS STEELS; STEELS; TEMPERATURE RANGE; TITANIUM ALLOYS; TITANIUM BASE ALLOYS; TUNGSTEN ADDITIONS; UNDERGROUND FACILITIES; VANADIUM ADDITIONS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Contract/Grant/Project number
- Contract FI1W/0032-D