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Title: Radioactive waste material disposal

Abstract

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Inventors:
; ;
Publication Date:
Research Org.:
Lockheed Martin Energy Syst Inc
OSTI Identifier:
119036
Patent Number(s):
US 5,461,185/A/
Application Number:
PAN: 8-230,156
Assignee:
PTO; SCA: 052001; PA: EDB-95:146576; SN: 95001477067
DOE Contract Number:
AC05-84OR21400
Resource Type:
Patent
Resource Relation:
Other Information: PBD: 24 Oct 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; SPENT FUELS; VITRIFICATION; OXIDATION; FUEL CANS; RADIOACTIVE WASTE PROCESSING; LEAD OXIDES; WASTE FORMS; ELECTROCHEMICAL CELLS; IRON OXIDES

Citation Formats

Forsberg, C.W., Beahm, E.C., and Parker, G.W. Radioactive waste material disposal. United States: N. p., 1995. Web.
Forsberg, C.W., Beahm, E.C., & Parker, G.W. Radioactive waste material disposal. United States.
Forsberg, C.W., Beahm, E.C., and Parker, G.W. 1995. "Radioactive waste material disposal". United States. doi:.
@article{osti_119036,
title = {Radioactive waste material disposal},
author = {Forsberg, C.W. and Beahm, E.C. and Parker, G.W.},
abstractNote = {The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1995,
month =
}
  • The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.
  • In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.
  • A packaging system for storage of containers of low-level radioactive waste consisting of a concrete shell structure that houses the containers and a dry filler material that surrounds them. Void volume in the filler material is saturated with water, and during free-fall descent to the seafloor, a pressure compensation means equalizes pressures inside and outside the packaging structure and forces the filler material into intimate contact about the drums; on the seafloor, the filler material hardens to produce a highly secure barrier to any leaking of radioactive waste.
  • This patent describes a cartridge for permanent disposal of solid radioactive particulate waste, comprising; a liquid impervious casing having an upper end cover, a lower end cover and a side wall extending between the covers, the casing enclosing a waste storage region; ferromagnetic fibrous material defining a waste retaining matrix and filling a major portion of the waste storage region; means defining an inlet conduit extending through the upper end cover and axially of the casing through the waste storage region, and opening into the waste storage region in the vicinity of the lower and end cover; and means definingmore » first and second outlet conduits extending through the upper end cover and opening into the waste storage region in the vicinity of the upper end cover.« less
  • Systems, apparatus and methods are disclosed for disposing of radioactive waste materials by placing them into a container such as a steel drum, together with cement or other solidifying agent and water or other suitable liquid in amounts sufficient to provide eventually a solidified mixture of predetermined amounts of cement or other solidifying agent and radioactive material, closing the drum, agitating the mixture in the drum for mixing the contents, and then storing the drum for at least a period of time sufficient to permit partial decay of radioactive materials or to await available time for shipment. Also disclosed aremore » remotely controlled apparatus for handling both empty and filled drums, for placing the drums in and removing drums from enclosed drumming equipment where they have been filled and agitated, for accurately placing the drums containing radioactive material in storage, and for removing the drums from storage and loading them on a vehicle for transportation. All of these operations are done by remote control with a high degree of safety to the operators and maintenance personnel from radiation and freedom of the ambient from radiation pollution.« less