Study of the behavior of high activity waste produced during the regeneration of fast reactor fuel elements by the gaseous fluoride method
Description
The composition and certain physicochemical and radiation properties of waste obtained from reprocessing BOR-60 fuel by the gaseous fluoride method were studied on an experimental stand. It was found that from 80 to 85 percent of the total activity is concentrated in the fluorination cakes. From thermographic analysis, measurement of radiation-induced gas evolution and composition of the gaseous phase, it is concluded that the waste must be canned. Compatibility of carbon steel, austenitic steel, and nickel with low-activity fluoride cakes was studied. It is shown that the corrosion of these materials increases with temperature and moisture content of the medium. In the first stage of waste disposal, hermetic storage in special containers of stainless steel or nickel is recommended. From their corrosion resistance in low-activity fluoride cakes, the wall temperatures of containers made of St. 3 should not exceed 1000C, Kh18N10T 2300C, and nickel 3000C. Later, after cooling and a decrease in the γ activity of the waste (10 to 15 years), they can be reprocessed to recover valuable components (Am, Cm, etc.) and then buried. 5 tables
Availability note (English)
MF available from INIS under the Report Number.Additional details
Additional titles
- Augmented title (English)
- Compatibility of materials with fluoride cakes
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- ERDA-tr--204
Conference
- Title
- IAEA meeting on LMFBR fuel reprocessing.
- Dates
- 17 May 1976.
- Place
- Leningrad, Union of Soviet Socialist Republics (USSR).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8297050
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOR-60 REACTOR; CARBON STEELS; CHEMICAL PROPERTIES; COMPATIBILITY; CORROSION RESISTANCE; DEGASSING; FLUORIDE VOLATILITY PROCESS; NICKEL; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTES; REPROCESSING; SPENT FUEL ELEMENTS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; EXTRACTIVE METALLURGY; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MANAGEMENT; METALLURGY; METALS; POWER REACTORS; PYROMETALLURGY; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- Translation of Russian report CONF-760576--6.