Process for making protective barriers against radioactive products

• US 4,300,056 A
• Filed: 02/26/1979
• Issued: 11/10/1981
• Est. Priority Date: 08/03/1978
• Status: Expired due to Term

• Current Assignee: Francis Gagneraud
• Original Assignee: Francis Gagneraud
• Inventors: Gagneraud, Francis
• Primary Examiner(s): Anderson, Bruce C.
• Application Number:
  US06/014,963
• Time in Patent Office: 988 Days
• Field of Search: 250/506, 250/507, 250/515, 250/517, 250/518, 252/301.1 W, 252/478
• US Class Current: 250/517.1
• CPC Class Codes: G21F 9/302 in an inorganic matrix
• CPC Class Codes: G21F 9/34 Disposal of solid waste

Abstract

The outside environment is shielded from radioactive materials by surrounding the radioactive material with an enclosure formed from slowly cooled molten slag or scoria coming from a ferrous or nonferrous metal making operation. The enclosure may comprise walls, slabs or blocks of such material formed into a building, a conduit of such material for movement of radioactive effluents or a metal container separated from an outer metal container by such material.

Claims

1. A process for shielding radiation emanating from radioactive products to permit storage, handling and shipping without danger, comprising:

placing elements made up of materials selected from the group consisting of molten slag and scorias, coming from a ferrous or nonferrous metal production operation, between the radioactive products and the outside environment to be protected.

2. A process in accordance with claim 1 wherein said elements are shaped into walls, slabs or blocks and constructed into enclosed spaces sheltering the radioactive products.

3. A process in accordance with claim 1 wherein said elements are shaped into conduits for movement of radioactive products in the form of radioactive effluents.

4. A process in accordance with claim 1 wherein the radioactive products comprise solid or pasty radioactive wastes enclosed in a metal container and said placing step comprises wedging said metal container within a larger empty outside drum such as to leave a space between the container and the drum on all sides, pouring molten slag or scoria into the free space between the container and the drum, and cooling slowly to avoid any cracking.

5. A process in accordance with claim 4, further including, after said pouring step and before said cooling step, covering the surface of the slag with an insulating or exothermal product of the perlite or vermiculite type, to which metallic powder has been added, thereby allowing gas trapped in the slag to escape and thus increase the density of the protective slag layer.

6. A process in accordance with claim 1 wherein said molten slags and scorias came from a blast furnace, a steel mill, a foundry, a ferroalloy fabrication plant, a lead-zinc smelter, a copper smelting plant, or a plant for the fabrication of phosphorus by electric oven.

7. A process in accordance with claim 6 wherein the slags and scorias have a slight basicity index and contain heavy metal oxides.

8. A process in accordance with claim 6 wherein the molten slags and scorias have added thereto one or more slag substances selected from the group consisting of sodium borate, sodium carbonate, siliceous sand and iron oxides, in an amount sufficient to lower the solidification temperature and/or increase the fluidity of the molten slag.

9. A container for the storage of solid or pasty radioactive wastes comprising a metal container within and spaced from a larger metal drum, the free space between said container and said drum being filled with a material formed by pouring molten slag or scoria coming from a ferrous or nonferrous metal production operation into said free space and allowing said molten slag or scoria to cool slowly to avoid cracking.

10. A container in accordance with claim 9 wherein said molten slag or scoria used to fill said free space has a slight basicity index and contains heavy metal oxides.