Degradation of a N06690 borescope in a radioactive waste/glass melter system
Description
Radioactive liquid waste from nuclear materials production processes wi11 be vitrified in the Defense Waste Process Facility (DWPF) melter. The melter borescope outer housing, fabricated from N06690, was severely degraded by the combined effects of corrosion and oxidation after only five months of non radioactive operation. The melter was idled and not being fed over 85% of the time during the cold run operations. The borescope was designed to perform in an oxygen rich, chloride containing environment with temperatures approaching 900 degree C (1650 degree F). The housing was designed for a minimum of two years of continuous service in the DWPF melter. Air and steam were purged through the borescope and swept over the optics assembly to keep molten glass and volatile gases from depositing on the lens cover. Upon exiting the borescope the air passes through a N06690 orifice and enters the melter. Severe oxidation was observed around the orifice. Extensive material loss was also observed on the side of the outer housing which protrudes through the dome of the melter. Redesign of the borescope is currently underway and will include a new set of optics that will allow the size of the orifice to be significantly decreased, thus reducing the amount of air necessary to keep the lens cover clean. Application of a duplex diffusion coating, consisting of chromium and aluminum, on the end of the borescope outer housing and the use of an inert gas purge are also being considered
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95017479; NTIS; US Govt. Printing Office Dep.Files
27016258.pdf
Files
(426.6 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:3f33a352febd7de729d02ca35902cf81
|
426.6 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- WSRC-MS--95-0192
Conference
- Title
- 2. international conference on heat resistant materials.
- Dates
- 11-14 Sep 1995.
- Place
- Gatlinburg, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27016258
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM SILICATES; ALUMINIUM SULFATES; BORESCOPES; CERAMIC MELTERS; CHROMIUM OXIDES; CORROSION; CORROSIVE EFFECTS; CRACKS; INCONEL 690; NICKEL OXIDES; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTES; SODIUM SILICATES; SODIUM SULFATES; VITRIFICATION
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALLOY-NI59CR30FE9; ALLOYS; ALUMINIUM COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM COMPOUNDS; CORROSION RESISTANT ALLOYS; ELECTRIC FURNACES; FURNACES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NICKEL COMPOUNDS; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; SILICATES; SILICON COMPOUNDS; SODIUM COMPOUNDS; SULFATES; SULFUR COMPOUNDS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WASTES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-950908--4.