Radioactive waste solidification method

Patent metadata

Field	Value
Publication number	US-9336914-B2
Application number	US-201514799997-A
Country	US
Kind code	B2
Filing date	Jul 15, 2015
Priority date	Jul 23, 2014
Publication date	May 10, 2016
Grant date	May 10, 2016

Abstract

A radioactive waste (zeolite to which Cs-137 was adsorbed) in a waste tank and a glass raw material (soda lime glass) in a glass raw material tank are supplied into a solidifying vessel. Graphite in a graphite tank is also supplied into the solidifying vessel. The solidifying vessel is filled with a mixture of the radioactive waste, glass raw material, and graphite and is then disposed in an adiabatic vessel. The radioactive waste and glass raw material in the adiabatic vessel are heated by thermal energy generated due to radiation emitted from Cs-137. The heat is transferred to the peripheral portion of the solidifying vessel through the graphite, raising the temperature of the peripheral portion. The glass raw material is melted and enters clearances among the radioactive waste, producing a vitrified radioactive waste. This radioactive waste solidification method can shorten a time taken to produce a vitrified radioactive waste.

First claim

What is claimed is:

1. A radioactive waste solidification method comprising steps of:
supplying a radioactive waste including a radioactive nuclide, a glass raw material, and graphite into a first vessel;
disposing the first vessel in which the radioactive waste, the glass raw material, and the graphite exist, in an adiabatic area in a second vessel;
heating the radioactive waste and the glass raw material existing in the first vessel disposed in an adiabatic area in the second vessel by heat generated by radiation emitted from the radioactive nuclide and melting the glass raw material in the first vessel; and
producing a vitrified radioactive waste by the melt of the heated glass raw materials.

2. The radioactive waste solidification method according to claim 1 , wherein in the disposal of the first vessel, in which the radioactive waste, the glass raw material, and the graphite exist, into the adiabatic area, this first vessel is disposed in an adiabatic area formed in an adiabatic vessel being the second vessel.

3. The radioactive waste solidification method according to claim 1 , wherein in the disposal of the first vessel, in which the radioactive waste, the glass raw material, and the graphite exist, into the adiabatic area, this first vessel is disposed in a pressure reducing vessel being the second vessel, and a pressure in a space in which the first vessel is disposed is reduced to form the adiabatic area, the space being formed in the sealed pressure reducing vessel.

4. The radioactive waste solidification method according to claim 1 , wherein a temperature of the first vessel disposed in the adiabatic area in the second vessel is measured, and a flow rate of gas to be supplied to the adiabatic area in the second vessel is adjusted based on the measured temperature.

5. The radioactive waste solidification method according to claim 3 , wherein a temperature of the first vessel disposed in the adiabatic area in the second vessel is measured, and a pressure in the adiabatic area in the second vessel is controlled.

6. The radioactive waste solidification method according to claim 2 , wherein a temperature of the first vessel disposed in the adiabatic area in the second vessel is measured, and a flow rate of gas to be supplied to the adiabatic area in the second vessel is adjusted based on the measured temperature.

7. The radioactive waste solidification method according to claim 3 , wherein a temperature of the first vessel disposed in the adiabatic area in the second vessel is measured, and a flow rate of gas to be supplied to the adiabatic area in the second vessel is adjusted based on the measured temperature.

8. A radioactive waste solidification method comprising steps of:
supplying a radioactive waste including a radioactive nuclide, and a glass raw material into each of a plurality of waste filling areas, the plurality of waste filling areas being formed with thermally conductive members in a first vessel;
disposing the first vessel in which the radioactive waste and the glass raw material exist, in an adiabatic area in a second vessel;
heating the radioactive waste and the glass raw material existing in each waste filling area in the first vessel disposed in the adiabatic area in the second vessel by heat generated by radiation emitted from the radioactive nuclide and melting the glass raw material in the first vessel; and
producing a vitrified radioactive waste by the melt of the heated glass raw materials.

Assignees

• Hitachi Ge Nuclear Energy Ltd

Inventors

• Itou Tsuyoshi
• Noshita Kenji
• Asano Takashi

Classifications

• G21F9/305 Primary

  Glass or glass like matrix (C03B5/005 takes precedence; compositional aspects C03C) · CPC title

• G21F9/30

  Processing (separating different isotopes of the same chemical element B01D59/00) · CPC title

• G21F9/28

  Treating solids · CPC title