Published 1976 | Version v1
Report

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).

Optional Information

Notes
Translation of Russian report CONF-760576--6.