EP2919237B1 - Radioactive waste solidification method - Google Patents
Radioactive waste solidification method Download PDFInfo
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- EP2919237B1 EP2919237B1 EP15158743.3A EP15158743A EP2919237B1 EP 2919237 B1 EP2919237 B1 EP 2919237B1 EP 15158743 A EP15158743 A EP 15158743A EP 2919237 B1 EP2919237 B1 EP 2919237B1
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- European Patent Office
- Prior art keywords
- vessel
- radioactive waste
- glass raw
- raw materials
- adiabatic
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- 239000002901 radioactive waste Substances 0.000 title claims description 193
- 230000008023 solidification Effects 0.000 title claims description 54
- 238000007711 solidification Methods 0.000 title claims description 54
- 238000000034 method Methods 0.000 title claims description 44
- 239000011521 glass Substances 0.000 claims description 189
- 239000002994 raw material Substances 0.000 claims description 154
- 239000002913 vitrified radioactive waste Substances 0.000 claims description 50
- 230000005855 radiation Effects 0.000 claims description 28
- 230000002285 radioactive effect Effects 0.000 claims description 17
- 238000010438 heat treatment Methods 0.000 claims description 4
- 239000005361 soda-lime glass Substances 0.000 description 17
- 239000000126 substance Substances 0.000 description 17
- 239000003463 adsorbent Substances 0.000 description 14
- -1 mordenitem Chemical compound 0.000 description 14
- 239000002699 waste material Substances 0.000 description 14
- 238000002844 melting Methods 0.000 description 13
- 230000008018 melting Effects 0.000 description 13
- 239000002927 high level radioactive waste Substances 0.000 description 12
- 239000000203 mixture Substances 0.000 description 11
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N Iron oxide Chemical compound [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 10
- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 description 10
- 229910052720 vanadium Inorganic materials 0.000 description 8
- LEONUFNNVUYDNQ-UHFFFAOYSA-N vanadium atom Chemical compound [V] LEONUFNNVUYDNQ-UHFFFAOYSA-N 0.000 description 8
- 229910021536 Zeolite Inorganic materials 0.000 description 7
- 239000005388 borosilicate glass Substances 0.000 description 7
- 150000001875 compounds Chemical class 0.000 description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 239000010457 zeolite Substances 0.000 description 7
- 239000004568 cement Substances 0.000 description 6
- 230000000694 effects Effects 0.000 description 6
- 239000007789 gas Substances 0.000 description 6
- 235000013980 iron oxide Nutrition 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- UNYSKUBLZGJSLV-UHFFFAOYSA-L calcium;1,3,5,2,4,6$l^{2}-trioxadisilaluminane 2,4-dioxide;dihydroxide;hexahydrate Chemical compound O.O.O.O.O.O.[OH-].[OH-].[Ca+2].O=[Si]1O[Al]O[Si](=O)O1.O=[Si]1O[Al]O[Si](=O)O1 UNYSKUBLZGJSLV-UHFFFAOYSA-L 0.000 description 5
- 229910052676 chabazite Inorganic materials 0.000 description 5
- 230000020169 heat generation Effects 0.000 description 5
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 4
- 239000011491 glass wool Substances 0.000 description 4
- 239000000843 powder Substances 0.000 description 4
- 239000010857 liquid radioactive waste Substances 0.000 description 3
- 239000002900 solid radioactive waste Substances 0.000 description 3
- JYIBXUUINYLWLR-UHFFFAOYSA-N aluminum;calcium;potassium;silicon;sodium;trihydrate Chemical compound O.O.O.[Na].[Al].[Si].[K].[Ca] JYIBXUUINYLWLR-UHFFFAOYSA-N 0.000 description 2
- 238000009933 burial Methods 0.000 description 2
- 229910001603 clinoptilolite Inorganic materials 0.000 description 2
- 239000013078 crystal Substances 0.000 description 2
- 239000000945 filler Substances 0.000 description 2
- 239000006260 foam Substances 0.000 description 2
- VBMVTYDPPZVILR-UHFFFAOYSA-N iron(2+);oxygen(2-) Chemical class [O-2].[Fe+2] VBMVTYDPPZVILR-UHFFFAOYSA-N 0.000 description 2
- 239000005355 lead glass Substances 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000005365 phosphate glass Substances 0.000 description 2
- 239000010453 quartz Substances 0.000 description 2
- 239000005368 silicate glass Substances 0.000 description 2
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 2
- 229920003043 Cellulose fiber Polymers 0.000 description 1
- JOYRKODLDBILNP-UHFFFAOYSA-N Ethyl urethane Chemical compound CCOC(N)=O JOYRKODLDBILNP-UHFFFAOYSA-N 0.000 description 1
- ISWSIDIOOBJBQZ-UHFFFAOYSA-N Phenol Chemical compound OC1=CC=CC=C1 ISWSIDIOOBJBQZ-UHFFFAOYSA-N 0.000 description 1
- 239000004111 Potassium silicate Substances 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000007799 cork Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 238000001027 hydrothermal synthesis Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000000465 moulding Methods 0.000 description 1
- 229920006327 polystyrene foam Polymers 0.000 description 1
- NNHHDJVEYQHLHG-UHFFFAOYSA-N potassium silicate Chemical compound [K+].[K+].[O-][Si]([O-])=O NNHHDJVEYQHLHG-UHFFFAOYSA-N 0.000 description 1
- 229910052913 potassium silicate Inorganic materials 0.000 description 1
- 235000019353 potassium silicate Nutrition 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/305—Glass or glass like matrix
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
Definitions
- the present invention relates to a radioactive waste solidification method, and more particularly to a radioactive waste solidification method suitable to processing of high-dose radioactive waste having a high radioactive level.
- Radioactive waste generated from a nuclear facility and the like are solidified with cement or glass and are then converted to a form suitable for storage, transportation, and burial processing.
- Solidification with cement of various types of solidification processing is a method in which radioactive waste is solidified with cement and water, so this method is inexpensive and is also advantageous in that processing is easily performed.
- moisture included in the radioactive solidified body generated by the cement solidification is subjected to radiolysis, generating a hydrogen gas.
- This hydrogen gas may affect the solidified body itself or a facility after burial processing (refer to Japanese Patent Laid-open No. 2007-132787 ). Therefore, in a radioactive waste solidification method described in Japanese Patent Laid-open No.
- radioactive waste, cement, and water are mixed in a drum which is a solidifying vessel to produce a solidified body, and the solidified body is dried to eliminate moisture from the solidified body through heating or pressure reduction at a stage in which uniaxial compression strength is 1.5 MPa or more and is 75% or less of predicted strength.
- Japanese Patent Laid-Open No. 62(1987)-124499 describes a radioactive waste solidification method.
- solid or liquid radioactive waste are mixed with glass with a low melting point (the melting point is 400°C to 800°C), and the resulting mixture of the waste and glass is subjected to molding and baking or is melted by being heated and a solidified body is produced.
- Japanese Patent Laid-Open No. 62(1987)-165198 describes a hydrothermal solidification method for high-level radioactive waste.
- this hydrothermal solidification method for high-level radioactive waste high-level radioactive waste, glass, and quartz powder are mixed, and the resulting mixture is further mixed with water. This mixture is supplied into a canister. The mixture in the canister is heated to 300°C due to decay heat of the high-level radioactive waste, producing a solidified body through a hydrothermal reaction.
- the surfaces of glass and quartz powder are melted due to decay heat and high-level radioactive waste is bonded.
- solidification of high-dose radioactive waste solidification with glass in which a hydrogen gas due to radiation is not generated is preferable.
- conventional methods of solidification with glass are problematic in that a large melting facility is needed, the hydrothermal solidification method for high-level radioactive waste described in Japanese Patent Laid-Open No. 62(1987)-124499 can solve the above problem because decay heat of high-level radioactive waste is used to melt glass and crystal powder.
- high-level radioactive waste is solidified in a hydrothermal solidification method in which added water is used.
- the high-level radioactive waste is solidified by melting only the surfaces of glass and crystal powder.
- the produced solidified body is a non-uniform substance including water and steam and radioactive nuclides are thereby likely to leak from the solidified body.
- An object of the present invention is to provide a radioactive waste solidification method that can produce a uniform vitrified radioactive waste through uniform heating without having to use a melting facility.
- a feature of the present invention for attaining the above object is a radioactive waste solidification method comprising steps of:
- the first vessel in which the radioactive waste including radioactive nuclides and glass raw materials exist is disposed in the adiabatic area in the second vessel and the glass raw materials in the first vessel are melted in the adiabatic area by heat generated from radiation emitted from the radioactive nuclides, a melting facility is not needed and the radioactive waste and glass raw materials in the first vessel are evenly heated, so a uniform vitrified radioactive waste can be obtained.
- radioactive waste and glass raw materials are uniformly heated without having to use a melting facility and a uniform vitrified radioactive waste can be obtained.
- the inventors made various studies and found that when a solidifying vessel filled with a mixture of a radioactive waste and glass raw materials, which are solidifying materials, is disposed in an adiabatic region formed by, for example, surrounding the solidifying vessel with an adiabatic member or vacuating the interior of the solidifying vessel and the glass raw materials in the solidifying vessel are melted by using decay heat of radioactive nuclides included in the radioactive waste, the glass raw materials in the solidifying vessel are uniformly heated and a uniform solidified body of radioactive waste can thereby be produced due to the melted glass raw materials.
- the temperature in the glass raw materials in the solidifying vessel can be substantially uniformly raised to a temperature needed to melt the glass raw materials, regardless of the positions of the glass raw materials in the solidifying vessel.
- the solidifying vessel filled with the radioactive waste and glass raw materials is uniformly heated, and a more uniform solidified body of radioactive wastes can thereby be produced.
- a radioactive waste solidification method according to embodiment 1, which is a preferred embodiment of the present invention, will be described with reference to FIGs. 1 and 2 .
- 100 kg of high-dose radioactive waste that includes 10 16 Bq of Cs-137 (for example, zeolite to which Cs-137 has been adsorbed) as high-dose radioactive waste and 100 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel and a vitrified radioactive waste is produced.
- the radioactive waste solidification method of the present embodiment will be described below with reference to the procedure illustrated in FIG. 1 .
- Radioactive waste and glass raw materials are supplied into a solidifying vessel (step S1). Specifically, a metallic (or ceramic) vacant solidifying vessel (a first vessel) 3 is disposed below a waste tank 1 in which radioactive waste 4 has been stored. High-dose radioactive waste 4 that include 10 16 Bq of Cs-137 in the waste tank 1 are supplied by 100 kg into the solidifying vessel 3 through a waste supply pipe 2.
- the radioactive waste 4 supplied into the solidifying vessel 3 is, for example, zeolite to which the above Cs-137 was adsorbed. After that, the solidifying vessel 3 filled with the radioactive waste 4 is moved to a position immediately below a glass raw material tank 1A.
- 100 kg of soda lime glass which is a glass raw material 6 in the glass raw material tank 1A, is supplied into the solidifying vessel 3 through a glass raw material supply pipe 5.
- Glass raw materials 6 may be supplied into the solidifying vessel 3 first, and after the supply of the glass raw materials 6, radioactive waste 4 may be supplied into the solidifying vessel 3.
- the glass raw materials 6 and radioactive waste 4 may be supplied into the solidifying vessel 3 at the same time.
- the radioactive waste 4 supplied into the solidifying vessel 3 may be a liquid radioactive waste, a solid radioactive waste, or a mixture of a liquid radioactive waste and a solid radioactive waste.
- Adiabatic processing is performed for the solidifying vessel 3 filled with the radioactive waste 4 and the glass raw materials 6 is melted (step S2). Specifically, the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 is disposed in an adiabatic vessel (a second vessel) 7 with its upper end open.
- the adiabatic vessel 7 has a lid 7A, which is removable, at the upper end.
- the lid 7A is removed, making the solidifying vessel 3 upwardly open. In this state, the solidifying vessel 3 is disposed in the adiabatic vessel 7 from above.
- the lid 7A is attached to the upper end of the adiabatic vessel 7 to seal the adiabatic vessel 7 in which the solidifying vessel 3 is disposed.
- the adiabatic vessel 7 and lid 7A are made of an adiabatic material. For example, they are made of glass wool.
- an adiabatic area which is thermally insulated by the adiabatic vessel 7, is formed.
- the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 are disposed in this adiabatic area.
- the adiabatic vessel 7 has a double structure of a metallic outer vessel (not shown) and an inner vessel (not shown) which is disposed in the outer vessel.
- Glass wool is disposed in an annular area between the outer vessel and the inner vessel and in a space between a bottom of the outer vessel and a bottom of the inner vessel.
- An upper end of the annular area between the outer vessel and the inner vessel is sealed with a ring-shaped plate attached to both upper ends of the outer vessel and inner vessel.
- the lid 7A is formed by a metal hollow case (not shown) filled with glass wool.
- the adiabatic processing means a processing to suppress heat of the solidifying vessel 3 from being emitted to the outside.
- heat decay heat
- the adiabatic vessel 7 sealed with the lid 7A Emission of this decay heat to the outside is suppressed by the adiabatic vessel 7 sealed with the lid 7A, and the decay heat is stored in the interior of the adiabatic vessel 7 sealed with the lid 7A, that is, in the adiabatic vessel 7 sealed with the lid 7A.
- the glass raw materials 6 in the solidifying vessel 3 are heated due to this decay heat and melted.
- the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 is surrounded by the adiabatic vessel 7 and lid 7A, the solidifying vessel 3 is heated by decay heat of the radioactive waste 4.
- the temperatures of the radioactive waste 4 and glass raw materials 6 stored in the solidifying vessel 3 in the adiabatic vessel 7 become substantially uniform; these temperature do not become non-uniform depending on the positions of the radioactive wastes 4 and glass raw materials 6 in the solidifying vessel 3.
- the temperatures of the radioactive waste 4 and glass raw materials 6 are each raised by about 66°C per hour. Soda lime glass, which is the glass raw material 6, is melted due to this temperature rise and flows into clearances among the radioactive waste 4.
- the radioactive waste 4 and glass raw materials 6 are mixed with an agitator. If a liquid is included in the radioactive waste 4, this liquid is heated by the heat described above and is turned into a vapor.
- a vitrified radioactive waste is produced (step S3). Specifically, since some heat is emitted to the outside through the adiabatic vessel 7 and lid 7A, an actual temperature rise rate in the solidifying vessel 3 is lower than 66°C/h. However, a temperature rise is continued with time, so all glass raw materials 6 in the solidifying vessel 3 are melted. As a result, clearances between radioactive waste 4 are filled with the melted substances of the glass raw materials 6, and a vitrified radioactive waste 9 in which a glass-solidified substance 8 exists in the solidifying vessel 3 is produced. In the vitrified radioactive waste 9, the radioactive waste 4 have been integrated by the melted substances of the glass raw materials 6. After the vitrified radioactive waste 9 has been produced, the lid 7A is removed.
- the vitrified radioactive waste 9 is taken out of the adiabatic vessel 7 and a lid (not shown) is attached to the solidifying vessel 3 of the vitrified radioactive waste 9 to seal it. Thereafter, the vitrified radioactive waste 9 is stored as a waste body at a prescribed storage place (not shown).
- the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 is surrounded by the adiabatic vessel 7 sealed with the lid 7A, radiation emitted as a result of the decay of radioactive nuclides included in the radioactive waste 4 is absorbed in the radioactive waste 4 and glass raw materials 6 disposed in the adiabatic area in the adiabatic vessel 7 and the resulting thermal energy (decay heat) heats the radioactive waste 4 and glass raw materials 6. Therefore, the radioactive waste 4 and glass raw materials 6 existing in the adiabatic area are uniformly heated, so the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 become more uniform. This suppresses corrosion of the solidifying vessel 3 at high temperatures and volatilization of the radioactive wastes 4. In addition, a uniform vitrified radioactive waste of the radioactive waste 4 is obtained. This vitrified radioactive waste is stable.
- the radioactive waste 4 and glass raw materials 6 are heated by thermal energy generated by the absorption of radiation emitted due to the decay of the radioactive waste 4 in the solidifying vessel 3.
- a melting facility to melt the glass raw materials 6 is not needed, unlike solidification of radioactive waste with glass, which is described in Japanese Patent Laid-open No. 2011-46996 . That is, a simple system can be used to solidify the radioactive waste 4 with the glass raw materials 6.
- zeolite to which Cs-137 was adsorbed was supplied into the solidifying vessel 3 as the radioactive waste 4 and was solidified with the glass raw materials 6.
- clinoptilolite, mordenitem, chabazite, insoluble ferrocyanide, or a titanate compound may be supplied into the solidifying vessel 3 and may be solidified by melting the glass raw materials 6 by the decay heat, as the radioactive waste 4.
- any one of silicate glass and borosilicate glass may be used as the glass raw material 6.
- any one of lead glass, phosphate glass, and vanadium-based glass, which have a softening point lower than soda lime glass, silicate glass, and borosilicate glass may be used.
- lead glass, phosphate glass, and vanadium-based glass solidification with glass is possible in an area at a lower temperature.
- the radioactive waste 4 can be solidified with glass in the solidifying vessel 3 and volatilization of the radioactive waste 4 can be suppressed to a lower level.
- Glass wool used in the adiabatic vessel 7 and lid 7A which are used adiabatic processing in the present embodiment, may be replaced with any one of cellulose fiber, which is a fiber-based adiabatic material, carbonized cork, urethane foam, phenol foam, polystyrene foam, and a potassium silicate board, which is a porous adiabatic material.
- cellulose fiber which is a fiber-based adiabatic material
- carbonized cork carbonized cork
- urethane foam urethane foam
- phenol foam phenol foam
- polystyrene foam polystyrene foam
- a potassium silicate board which is a porous adiabatic material.
- a radioactive waste solidification method according to embodiment 2, which is another preferred embodiment of the present invention, will be described with reference to FIGs. 1 and 2 .
- 100 kg of high-dose radioactive waste that includes 10 16 Bq of Sr-90 for example, spent adsorbents, for radioactive nuclides, the main component of which is a titanate compound to which Sr-90 was adsorbed (the adsorbent will be referred to as the titanate compound adsorbent)
- 100 kg of borosilicate glass which is a glass raw material, with a glass softening point of about 800°C were supplied into a solidifying vessel and a vitrified radioactive waste was produced.
- the radioactive waste solidification method of the present embodiment will be described below.
- a vitrified radioactive waste 9 is produced in steps S1, S2, and S3, as in embodiment 1.
- step S1 100 kg of high-dose radioactive waste 4, including 10 16 Bq of Sr-90, stored in the waste tank 1 and 100 kg of borosilicate glass, which is glass raw materials 6, stored in the glass raw material tank 1A are supplied into the solidifying vessel 3.
- the radioactive waste 4 supplied into the solidifying vessel 3 is a titanate compound adsorbent to which Sr-90 was adsorbed.
- step S2 is executed. That is, as in the embodiment 1, the solidifying vessel 3 which was filled with the radioactive waste 4 and glass raw materials 6 is disposed in the adiabatic vessel 7, and the lid 7A is attached to the adiabatic vessel 7 to seal it. Radiation emitted by the decay of Sr-90 included in the radioactive waste 4 existing in the solidifying vessel 3 enclosed with the lid 7A and adiabatic vessel 7 is absorbed by the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 and is then converted to thermal energy. The radioactive waste 4 and glass raw materials 6 enclosed with the lid 7A and adiabatic vessel 7 are heated due to this thermal energy and their temperatures are raised.
- the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 enclosed with the lid 7A and adiabatic vessel 7 become substantially uniform; these temperatures do not become non-uniform depending on the positions of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3.
- An adiabatic area is formed in the sealed adiabatic vessel 7 as described above. In the present embodiment as well, the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 is disposed in this adiabatic area.
- the temperatures of the radioactive waste 4 and glass raw materials 6 are each raised by about 160°C per hour. Borosilicate glass, which is the glass raw material 6, is melted due to this temperature rise and flows into clearances among the radioactive waste 4.
- a vitrified radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through the adiabatic vessel 7 and lid 7A, an actual temperature rise rate in the solidifying vessel 3 is lower than 160°C/h. However, a temperature rise is continued with time, so all glass raw materials 6 in the solidifying vessel 3 are melted. As a result, clearances between radioactive waste 4 are filled with the molted substances of the glass raw materials 6, and a vitrified radioactive waste 9 in which a glass-solidified substance 8 exists in the solidifying vessel 3 is produced; in the vitrified radioactive waste 9, the radioactive waste 4 have been integrated by the melted substances of the glass raw materials 6.
- the vitrified radioactive waste 9 is taken out of the adiabatic vessel 7 and a lid (not shown) is attached to the solidifying vessel 3 of the vitrified radioactive waste 9 to seal it. Thereafter, the vitrified radioactive waste 9 is stored as a waste body at a prescribed storage place (not shown).
- the present embodiment can be obtained the effects generated in the embodiment 1.
- any one of glass raw materials described in embodiment 1 may be used as the glass raw material 6.
- the radioactive waste 4 solidified with the glass raw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, or insoluble ferrocyanide, besides a titanate compound adsorbent.
- a radioactive waste solidification method according to embodiment 3, which is another preferred embodiment of the present invention, will be described with reference to FIGs. 1 and 3 .
- 100 kg of high-dose radioactive waste that include 10 15 Bq of Cs-137 for example, a spent adsorbent, for radioactive nuclides, the main component of which is insoluble ferrocyanide and to which Cs-137 was adsorbed (the adsorbent will be referred to as the insoluble ferrocyanide compound adsorbent)
- 100 kg of vanadium-based glass, which is a glass raw material, with a glass softening point of about 300°C were supplied into a solidifying vessel and a vitrified radioactive waste was produced.
- the radioactive waste solidification method of the present embodiment will be described below.
- a vitrified radioactive waste 9 is produced in steps S1, S2 and S3, as in embodiment 1.
- a pressure reducing vessel (second vessel) 10 is used instead of the adiabatic vessel 7 used in step S2 in embodiments 1 and 2.
- 100 kg of insoluble ferrocyanide compound adsorbent, which is the radioactive waste 4 in the waste tank 1, and 100 kg of vanadium-based glass, which is the glass raw material 6 in the glass raw material tank 1A, are supplied into the solidifying vessel (first vessel) 3 in step S1.
- the solidifying vessel 3 into which the radioactive waste 4 and vanadium-based glass were supplied is then disposed in the pressure reducing vessel 10 in step S2.
- a lid 10A is attached to the pressure reducing vessel 10 to seal it.
- An exhaust pipe 12 connected to the pressure reducing vessel 10 is connected to a pressure reducing pump 11.
- an exhaust pipe 13 is connected to the pressure reducing pump 11.
- step S2 the pressure in the sealed pressure reducing vessel 10 is reduced as described below.
- the pressure reducing pump 11 is driven and an opening/closing valve (not shown) attached to the exhaust pipe 12 is opened.
- an opening/closing valve (not shown) attached to the exhaust pipe 12 is opened.
- the gas in the sealed pressure reducing vessel 10 in which the solidifying vessel 3 is disposed is released to the outside through the exhaust pipe 12.
- This exhaust of the gas by the exhaust pipe 12 is performed until the pressure in the pressure reducing vessel 10 drops to one-tenth the atmospheric pressure.
- the pressure reducing pump 11 is stopped and the opening/closing valve attached to the exhaust pipe 12 is closed.
- adiabatic performance is improved by a factor of about 10 as compared with the use of the adiabatic vessel 7.
- the solidifying vessel 3 When the solidifying vessel 3 is thermally insulated by pressure reduction as described above, radiation generated due to the decay of Cs-137 included in the radioactive waste 4 in the solidifying vessel 3 is absorbed by the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 and is then converted to thermal energy.
- the radioactive waste 4 and glass raw materials 6 enclosed with the lid 10A and pressure reducing vessel 10 and existing in the area at a reduced pressure (adiabatic area) are heated due to this thermal energy. Accordingly, the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 are raised. These temperatures become substantially uniform; these temperatures do not become non-uniform depending on the positions of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3.
- Cs-137 emits radiation with about 1.15 MeV of energy per disintegration, as described in embodiment 1.
- the radiation is converted to thermal energy.
- the temperatures of the radioactive waste 4 and glass raw materials 6 are each raised by about 6.6°C per hour.
- a vitrified radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through the adiabatic vessel 7 and lid 7A, an actual temperature rise rate in the solidifying vessel 3 is lower than 6.6°C/h. However, a temperature rise is continued with time, so all glass raw materials 6 in the solidifying vessel 3 are melted. As a result, clearances between radioactive waste 4 are filled with the molted substances of the glass raw materials 6, and a vitrified radioactive waste 9 in which a glass-solidified substance 8 exists in the solidifying vessel 3 is produced; in the vitrified radioactive waste 9, the radioactive waste 4 have been integrated by the melted substances of the glass raw materials 6.
- the vitrified radioactive waste 9 is taken out of the pressure reducing vessel 10 and a lid (not shown) is attached to the solidifying vessel 3 of the vitrified radioactive waste 9 to seal it. Thereafter, the vitrified radioactive waste 9 is stored as a waste body at a prescribed storage place (not shown).
- the present embodiment can be obtained the effects generated in the embodiment 1.
- the radioactive waste 4 and glass raw materials 6 existing in the adiabatic area in the sealed pressure reducing vessel 10 are uniformly heated, so the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 become more uniform.
- the solidifying vessel 3 including the radioactive waste 4 and glass raw materials 6 is disposed in the sealed pressure reducing vessel 10 and the pressure in the pressure reducing vessel 10 is reduced, so a desired adiabatic effect can be obtained by adjusting the degree of pressure reduction.
- any one of the glasses described in embodiment 1 may be used as the glass raw material 6.
- the radioactive waste 4 solidified with the glass raw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, or a titanate compound, besides an insoluble ferrocyanide compound adsorbent.
- a radioactive waste solidification method according to embodiment 4, which is another preferred embodiment of the present invention, will be described with reference to FIGs. 1 and 4 .
- 100 kg of high-dose radioactive waste that includes 10 15 Bq of Co-60 for example, a solid-state radioactive waste the main component of which is an iron oxide including Co-60 (the radioactive waste will be referred to as the iron oxide)
- 100 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel to produce a vitrified radioactive waste.
- the radioactive waste solidification method of the present embodiment will be described below.
- a vitrified radioactive waste 9 is produced in steps S1, S2 and S3, as in embodiment 1.
- the radioactive waste (for example, iron oxides) 4 and glass raw materials (soda-lime glass) 6 supplied into the solidifying vessel 3 are mixed with an agitator in step S1 and in adiabatic processing in step S2, the adiabatic vessel 7 to which an air supply pipe that has an air supply pump is connected and further, an exhaust pipe is also connected is used instead of the adiabatic vessel 7 used in step S2 in embodiments 1 and 2.
- 100 kg of iron oxide, which is the radioactive waste 4 supplied from the waste tank 1, and 100 kg of soda lime glass, which is the glass raw material 6 supplied from the glass raw material tank 1A, are supplied into the solidifying vessel 3 in step S1.
- an agitator 14 is inserted into the solidifying vessel 3 in step S1.
- the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 are mixed with this agitator 14.
- the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6 is disposed in the adiabatic vessel 7 in step S2.
- the lid 7A is attached to the adiabatic vessel 7 to seal it.
- An air supply pipe 17 to which an air supply pump 16 and an opening/closing valve (not shown) are attached and an exhaust pipe 18 to which an opening/closing valve (not shown) is attached are connected to the adiabatic vessel 7.
- a thermometer 19 is attached to the adiabatic vessel 7.
- adiabatic processing in step S2 is performed for the solidifying vessel 3 filled with the radioactive waste 4 and glass raw materials 6.
- Radiation emitted by the decay of Co-60 included in the radioactive waste 4 existing in the solidifying vessel 3 enclosed with the sealed adiabatic vessel 7 is absorbed by the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 and is then converted to thermal energy.
- the radioactive waste 4 and glass raw materials 6 enclosed with the lid 7A and adiabatic vessel 7 are heated due to this thermal energy and their temperatures are raised.
- the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 enclosed with the lid 7A and adiabatic vessel 7 become substantially uniform; these temperatures do not become non-uniform depending on the positions of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3.
- Co-60 emits radiation with about 2.5 MeV of energy per disintegration.
- this radiation is absorbed in the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3, the radiation is converted to thermal energy.
- the temperatures of the radioactive waste 4 and glass raw materials 6 are each raised by about 144°C per hour.
- step S3 a vitrified radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through the adiabatic vessel 7 and lid 7A, an actual temperature rise rate in the solidifying vessel 3 is lower than 144°C/h. However, a temperature rise is continued with time, so all glass raw materials 6 in the solidifying vessel 3 are melted. At that time, the temperature of the solidifying vessel 3 in the adiabatic vessel 7 is measured with the thermometer 19.
- the opening/closing valve attached to the air supply pipe 17 and the opening/closing valve attached to the exhaust pipe 18 are opened and the air supply pump 16 is driven.
- an external gas (air) is supplied into the interior of the adiabatic vessel 7 through the air supply pipe 17 and the temperature of the solidifying vessel 3 is maintained at an appropriate temperature.
- the air supplied into the adiabatic vessel 7 is exhausted to the outside of the adiabatic vessel 7 through the exhaust pipe 18.
- the amount of air to be supplied into the adiabatic vessel 7 according to the temperature of the solidifying vessel 3 can be adjusted by controlling the rotational speed of the air supply pump 16.
- the radioactive waste 4 As a result, clearances between the radioactive waste 4 are filled with the molted substances of the glass raw materials 6, and a vitrified radioactive waste 9 in which a glass-solidified substance 8 exists in the solidifying vessel 3 is produced; in the vitrified radioactive waste 9, the radioactive waste 4 have been integrated by the melted substances of the glass raw materials 6.
- the vitrified radioactive waste 9 is taken out of the adiabatic vessel 7 and a lid (not shown) is attached to the solidifying vessel 3 of the vitrified radioactive waste 9 to seal it. Thereafter, the vitrified radioactive waste 9 is stored as a waste body at a prescribed storage place (not shown).
- the present embodiment can be obtained the effects generated in the embodiment 1.
- the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 are mixed with the agitator 14, a uniform vitrified radioactive waste 9 can be produced in a shorter time.
- the amount of gas (for example, air) to be supplied into the adiabatic vessel 7 is adjusted based on the measured temperature of the solidifying vessel 3 in the adiabatic vessel 7, so that it is possible to prevent the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3, which are raised by heat generated due to the decay of radioactive nuclides (for example, Co-60), from exceeding a temperature necessary for glass solidification. Therefore, the evaporation of radioactive nuclides included in the radioactive waste 4 can be suppressed.
- the amount of gas to be supplied into the adiabatic vessel 7 can also be adjusted based on the measured temperature of the solidifying vessel 3. Since the temperature during solidification with glass is measured and the amount of gas to be supplied is controlled, the rate at which the glass raw materials 6 are cooled can be adjusted. This can suppress the vitrified radioactive waste 9 from being cracked due to thermal distortion.
- any one of the glasses described in embodiment 1 may be used as the glass raw materials 6.
- the radioactive waste 4 solidified with the glass raw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, an insoluble ferrocyanide compound, or a titanate compound, besides iron oxides.
- a radioactive waste solidification method according to embodiment 5, which is another preferred embodiment of the present invention, will be described with reference to FIG. 5 .
- 100 kg of high-dose radioactive waste that includes 10 16 Bq of Cs-137 (for example, zeolite to which Cs-137 was adsorbed) as high-dose radioactive waste and 300 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel to produce a vitrified radioactive waste.
- Cs-137 for example, zeolite to which Cs-137 was adsorbed
- soda lime glass which is a glass raw material
- a vitrified radioactive waste 9 is produced in steps S1, S2 and S3, as in embodiment 1.
- the radioactive waste 4 and glass raw materials 6 are supplied into the solidifying vessel 3 at the same time in step S1 and, in adiabatic processing in step S2, the pressure reducing vessel 10 is used as in embodiment 1.
- 100 kg of high-dose radioactive waste 4, including 10 16 Bq of Cs-137, supplied from the waste tank 1 and 300 kg of glass raw material 6 supplied from the glass raw material tank 1A are supplied into the solidifying vessel 3 at the same time in step S1.
- the radioactive waste 4 is spent adsorbent the main component of which is insoluble ferrocyanide and to which Cs-137 was adsorbed.
- the glass raw material 6 is soda lime glass.
- the radioactive waste 4 and glass raw materials 6 are mixed in the solidifying vessel 3.
- the mixed radioactive waste 4 and glass raw materials 6 will be referred to as the mixed filler 15.
- the solidifying vessel 3 filled with the mixed filler 15 is disposed in the pressure reducing vessel 10 in step S2, as in embodiment 3.
- the thermometer 19 is attached to the pressure reducing vessel 10.
- the lid 10A is attached to the pressure reducing vessel 10 to seal it. After that, the pressure reducing pump 11 is driven and the pressure in the sealed pressure reducing vessel 10 is reduced to one-tenth the atmospheric pressure, as in embodiment 3.
- the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3 are heated by thermal energy generated due to the decay of Cs-137 included in the radioactive waste 4.
- the temperatures of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3, which is thermally insulated from the outside, are thereby raised. These temperatures become substantially uniform; these temperatures do not become non-uniform depending on the positions of the radioactive waste 4 and glass raw materials 6 in the solidifying vessel 3.
- the glass raw materials 6 in the solidifying vessel 3 are melted and this molted glass raw materials 6 osmoses clearances among the radioactive waste 4.
- the pressure in the pressure reducing vessel 10 is controlled by supplying air to and exhausting air from the pressure reducing vessel 10 with the pressure reducing pump 11. As a result, the temperatures of the glass raw materials 6 are maintained at an appropriate temperature.
- Cs-137 emits radiation with about 1.15 MeV of energy per disintegration, as described above. Therefore, when the radioactive waste 4 includes 10 16 Bq of Cs-137, thermal energy at a heat generation rate of 1840 J/s is obtained. If the specific heat of the mixture of the radioactive waste (zeolite to which Cs-137 was adsorbed) 4 and glass raw material (soda lime glass) 6 is 0.5 J/(g.K), the temperatures of the radioactive waste 4 and glass raw materials 6 are each raised by about 33°C per hour.
- a vitrified radioactive waste 9 is produced. Specifically, a temperature rise is continued with time, so all glass raw materials 6 are melted. As a result, clearances between radioactive waste 4 are filled with the molted substances of the glass raw materials 6, and a vitrified radioactive waste 9 in which a glass-solidified substance 8 exists in the solidifying vessel 3 is produced; in the vitrified radioactive waste 9, the radioactive waste 4 have been integrated by the melted substances of the glass raw materials 6.
- the vitrified radioactive waste 9 is taken out of the pressure reducing vessel 10 and a lid (not shown) is attached to the solidifying vessel 3 of the vitrified radioactive waste 9 to seal it. Thereafter, the vitrified radioactive waste 9 is stored as a waste body at a prescribed storage place (not shown).
- any one of the glasses described in the first embodiment may be used as the glass raw materials 6.
- the radioactive waste 4 solidified with the glass raw material 6 may be clinoptilolite, mordenitem, chabazite, an insoluble ferrocyanide compound, or a titanate compound, besides zeolite.
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Description
- The present invention relates to a radioactive waste solidification method, and more particularly to a radioactive waste solidification method suitable to processing of high-dose radioactive waste having a high radioactive level.
- Radioactive waste generated from a nuclear facility and the like are solidified with cement or glass and are then converted to a form suitable for storage, transportation, and burial processing. Solidification with cement of various types of solidification processing is a method in which radioactive waste is solidified with cement and water, so this method is inexpensive and is also advantageous in that processing is easily performed. When high level radioactive waste is solidified with cement in a solidifying vessel, however, moisture included in the radioactive solidified body generated by the cement solidification is subjected to radiolysis, generating a hydrogen gas. This hydrogen gas may affect the solidified body itself or a facility after burial processing (refer to Japanese Patent Laid-open No.
2007-132787 2007-132787 - In solidification with glass in which water is not used, so even if a radioactive waste is at a high radioactive level, there is no fear that a hydrogen gas is generated. As described in Japanese Patent Laid-open No.
2011-46996 - Japanese Patent Laid-Open No.
62(1987)-124499 - Japanese Patent Laid-Open No.
62(1987)-165198 -
- [Patent Literature 1] Japanese Patent Application No.
2007-132787 - [Patent Literature 2] Japanese Patent Application No.
2011-46996 - [Patent Literature 3] Japanese Patent Application No.
62(1987)-124499 - [Patent Literature 4] Japanese Patent Application No.
62(1987)-165198 - As for solidification of high-dose radioactive waste, solidification with glass in which a hydrogen gas due to radiation is not generated is preferable. Although conventional methods of solidification with glass are problematic in that a large melting facility is needed, the hydrothermal solidification method for high-level radioactive waste described in Japanese Patent Laid-Open No.
62(1987)-124499 62(1987)-124499 - An object of the present invention is to provide a radioactive waste solidification method that can produce a uniform vitrified radioactive waste through uniform heating without having to use a melting facility.
- A feature of the present invention for attaining the above object is a radioactive waste solidification method comprising steps of:
- supplying radioactive waste including radioactive nuclides and glass raw materials into a first vessel;
- disposing the first vessel in which the radioactive waste and glass raw materials exist, in an adiabatic area in a second vessel;
- heating the radioactive waste and glass raw materials in the first vessel existing in the adiabatic area in the second vessel by heat generated by radiation emitted from the radioactive nuclides; and/or
- producing a vitrified radioactive waste by melt of the heated glass raw materials.
- According to the present invention, since the first vessel in which the radioactive waste including radioactive nuclides and glass raw materials exist is disposed in the adiabatic area in the second vessel and the glass raw materials in the first vessel are melted in the adiabatic area by heat generated from radiation emitted from the radioactive nuclides, a melting facility is not needed and the radioactive waste and glass raw materials in the first vessel are evenly heated, so a uniform vitrified radioactive waste can be obtained.
- According to the present invention, radioactive waste and glass raw materials are uniformly heated without having to use a melting facility and a uniform vitrified radioactive waste can be obtained.
-
-
FIG. 1 is a flowchart showing a processing procedure in a radioactive waste solidification method according toembodiment 1, which is a preferred embodiment of the present invention. -
FIG. 2 is an explanatory drawing showing a concrete example of a radioactive waste solidification method according toembodiment 1 shown inFIG. 1 . -
FIG. 3 is an explanatory drawing showing a radioactive waste solidification method according toembodiment 3, which is another preferred embodiment of the present invention. -
FIG. 4 is an explanatory drawing showing a radioactive waste solidification method according toembodiment 4, which is another preferred embodiment of the present invention. -
FIG. 5 is an explanatory drawing showing a radioactive waste solidification method according toembodiment 5, which is another preferred embodiment of the present invention. - The inventors made various studies and found that when a solidifying vessel filled with a mixture of a radioactive waste and glass raw materials, which are solidifying materials, is disposed in an adiabatic region formed by, for example, surrounding the solidifying vessel with an adiabatic member or vacuating the interior of the solidifying vessel and the glass raw materials in the solidifying vessel are melted by using decay heat of radioactive nuclides included in the radioactive waste, the glass raw materials in the solidifying vessel are uniformly heated and a uniform solidified body of radioactive waste can thereby be produced due to the melted glass raw materials. That is, much radiation energy is emitted from high-dose radioactive waste, so when the radioactive waste itself and glass raw materials, which are solidifying materials, absorb the emitted radiation energy, thermal energy into which the radiation energy has been converted is stored in the radioactive waste and glass raw materials. Accordingly, the temperature in the glass raw materials in the solidifying vessel can be substantially uniformly raised to a temperature needed to melt the glass raw materials, regardless of the positions of the glass raw materials in the solidifying vessel.
- Therefore, the solidifying vessel filled with the radioactive waste and glass raw materials is uniformly heated, and a more uniform solidified body of radioactive wastes can thereby be produced.
- Embodiments of the present invention in which the above study result is considered will be described below.
- A radioactive waste solidification method according to
embodiment 1, which is a preferred embodiment of the present invention, will be described with reference toFIGs. 1 and 2 . In the radioactive waste solidification method in the present embodiment, 100 kg of high-dose radioactive waste that includes 1016 Bq of Cs-137 (for example, zeolite to which Cs-137 has been adsorbed) as high-dose radioactive waste and 100 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel and a vitrified radioactive waste is produced. The radioactive waste solidification method of the present embodiment will be described below with reference to the procedure illustrated inFIG. 1 . - Radioactive waste and glass raw materials are supplied into a solidifying vessel (step S1). Specifically, a metallic (or ceramic) vacant solidifying vessel (a first vessel) 3 is disposed below a
waste tank 1 in whichradioactive waste 4 has been stored. High-doseradioactive waste 4 that include 1016 Bq of Cs-137 in thewaste tank 1 are supplied by 100 kg into the solidifyingvessel 3 through awaste supply pipe 2. In the present embodiment, theradioactive waste 4 supplied into the solidifyingvessel 3 is, for example, zeolite to which the above Cs-137 was adsorbed. After that, the solidifyingvessel 3 filled with theradioactive waste 4 is moved to a position immediately below a glass raw material tank 1A. 100 kg of soda lime glass, which is a glassraw material 6 in the glassraw material tank 1A, is supplied into the solidifyingvessel 3 through a glass rawmaterial supply pipe 5. Glassraw materials 6 may be supplied into the solidifyingvessel 3 first, and after the supply of the glassraw materials 6,radioactive waste 4 may be supplied into the solidifyingvessel 3. Alternatively, the glassraw materials 6 andradioactive waste 4 may be supplied into the solidifyingvessel 3 at the same time. Theradioactive waste 4 supplied into the solidifyingvessel 3 may be a liquid radioactive waste, a solid radioactive waste, or a mixture of a liquid radioactive waste and a solid radioactive waste. - Adiabatic processing is performed for the solidifying
vessel 3 filled with theradioactive waste 4 and the glassraw materials 6 is melted (step S2). Specifically, the solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6 is disposed in an adiabatic vessel (a second vessel) 7 with its upper end open. Theadiabatic vessel 7 has alid 7A, which is removable, at the upper end. When the solidifyingvessel 3 is to be disposed in theadiabatic vessel 7, thelid 7A is removed, making the solidifyingvessel 3 upwardly open. In this state, the solidifyingvessel 3 is disposed in theadiabatic vessel 7 from above. After that, thelid 7A is attached to the upper end of theadiabatic vessel 7 to seal theadiabatic vessel 7 in which the solidifyingvessel 3 is disposed. Theadiabatic vessel 7 andlid 7A are made of an adiabatic material. For example, they are made of glass wool. In the sealedadiabatic vessel 7, an adiabatic area, which is thermally insulated by theadiabatic vessel 7, is formed. The solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6 are disposed in this adiabatic area. - The
adiabatic vessel 7 has a double structure of a metallic outer vessel (not shown) and an inner vessel (not shown) which is disposed in the outer vessel. Glass wool is disposed in an annular area between the outer vessel and the inner vessel and in a space between a bottom of the outer vessel and a bottom of the inner vessel. An upper end of the annular area between the outer vessel and the inner vessel is sealed with a ring-shaped plate attached to both upper ends of the outer vessel and inner vessel. Thelid 7A is formed by a metal hollow case (not shown) filled with glass wool. - After that, adiabatic processing is performed on the solidifying
vessel 3 disposed in the sealedadiabatic vessel 7. The adiabatic processing means a processing to suppress heat of the solidifyingvessel 3 from being emitted to the outside. In the solidifyingvessel 3 that has been subjected to the adiabatic processing, heat (decay heat) is generated based on radiation emitted from Cs-137 included in theradioactive waste 4 in the solidifyingvessel 3. Emission of this decay heat to the outside is suppressed by theadiabatic vessel 7 sealed with thelid 7A, and the decay heat is stored in the interior of theadiabatic vessel 7 sealed with thelid 7A, that is, in theadiabatic vessel 7 sealed with thelid 7A. The glassraw materials 6 in the solidifyingvessel 3 are heated due to this decay heat and melted. - Since the solidifying
vessel 3 filled with theradioactive waste 4 and glassraw materials 6 is surrounded by theadiabatic vessel 7 andlid 7A, the solidifyingvessel 3 is heated by decay heat of theradioactive waste 4. The temperatures of theradioactive waste 4 and glassraw materials 6 stored in the solidifyingvessel 3 in theadiabatic vessel 7 become substantially uniform; these temperature do not become non-uniform depending on the positions of theradioactive wastes 4 and glassraw materials 6 in the solidifyingvessel 3. - For example, Cs-137, which is a radioactive nuclide included in the
radioactive waste 4, emits radiation with about 1.15 MeV of energy per disintegration. This radiation is absorbed in theradioactive waste 4 and glass raw materials (soda lime glass) 6 and is then converted to thermal energy (decay heat). Since theradioactive waste 4 filled in the solidifyingvessel 3 includes 1016 Bq of Cs-137, if radiation emitted from each Cs-137 is all absorbed in theradioactive wastes 4 and glassraw materials 6 in the solidifyingvessel 3, thermal energy of 1.15 MeV x 1016Bq (= 1.15E22 eV/s), that is, at a heat generation rate of 1840 J/s, is obtained. If the specific heat of the mixture of the radioactive waste (zeolite to which Cs-137 has been adsorbed) 4 and glass raw material (soda lime glass) 6 is 0.5 J/(g.K), the temperatures of theradioactive waste 4 and glassraw materials 6 are each raised by about 66°C per hour. Soda lime glass, which is the glassraw material 6, is melted due to this temperature rise and flows into clearances among theradioactive waste 4. Preferably, as described inembodiment 4 below, after theradioactive waste 4 and glassraw materials 6 have been supplied into the solidifyingvessel 3, they are mixed with an agitator. If a liquid is included in theradioactive waste 4, this liquid is heated by the heat described above and is turned into a vapor. - A vitrified radioactive waste is produced (step S3). Specifically, since some heat is emitted to the outside through the
adiabatic vessel 7 andlid 7A, an actual temperature rise rate in the solidifyingvessel 3 is lower than 66°C/h. However, a temperature rise is continued with time, so all glassraw materials 6 in the solidifyingvessel 3 are melted. As a result, clearances betweenradioactive waste 4 are filled with the melted substances of the glassraw materials 6, and a vitrifiedradioactive waste 9 in which a glass-solidifiedsubstance 8 exists in the solidifyingvessel 3 is produced. In the vitrifiedradioactive waste 9, theradioactive waste 4 have been integrated by the melted substances of the glassraw materials 6. After the vitrifiedradioactive waste 9 has been produced, thelid 7A is removed. Then, the vitrifiedradioactive waste 9 is taken out of theadiabatic vessel 7 and a lid (not shown) is attached to the solidifyingvessel 3 of the vitrifiedradioactive waste 9 to seal it. Thereafter, the vitrifiedradioactive waste 9 is stored as a waste body at a prescribed storage place (not shown). - In the present embodiment, since the solidifying
vessel 3 filled with theradioactive waste 4 and glassraw materials 6 is surrounded by theadiabatic vessel 7 sealed with thelid 7A, radiation emitted as a result of the decay of radioactive nuclides included in theradioactive waste 4 is absorbed in theradioactive waste 4 and glassraw materials 6 disposed in the adiabatic area in theadiabatic vessel 7 and the resulting thermal energy (decay heat) heats theradioactive waste 4 and glassraw materials 6. Therefore, theradioactive waste 4 and glassraw materials 6 existing in the adiabatic area are uniformly heated, so the temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 become more uniform. This suppresses corrosion of the solidifyingvessel 3 at high temperatures and volatilization of the radioactive wastes 4. In addition, a uniform vitrified radioactive waste of theradioactive waste 4 is obtained. This vitrified radioactive waste is stable. - As described above, the
radioactive waste 4 and glassraw materials 6 are heated by thermal energy generated by the absorption of radiation emitted due to the decay of theradioactive waste 4 in the solidifyingvessel 3. In the present embodiment, therefore, a melting facility to melt the glassraw materials 6 is not needed, unlike solidification of radioactive waste with glass, which is described in Japanese Patent Laid-open No.2011-46996 radioactive waste 4 with the glassraw materials 6. - In the present embodiment, zeolite to which Cs-137 was adsorbed was supplied into the solidifying
vessel 3 as theradioactive waste 4 and was solidified with the glassraw materials 6. In the present embodiment, however, clinoptilolite, mordenitem, chabazite, insoluble ferrocyanide, or a titanate compound may be supplied into the solidifyingvessel 3 and may be solidified by melting the glassraw materials 6 by the decay heat, as theradioactive waste 4. - As substitute for soda lime glass, any one of silicate glass and borosilicate glass may be used as the glass
raw material 6. Furthermore, as the glassraw material 6, any one of lead glass, phosphate glass, and vanadium-based glass, which have a softening point lower than soda lime glass, silicate glass, and borosilicate glass may be used. When one of lead glass, phosphate glass, and vanadium-based glass is used, solidification with glass is possible in an area at a lower temperature. Therefore, even under conditions in which the amount of heat generated by the decay of theradioactive waste 4 in the solidifyingvessel 3 is low and in which a highly adiabatic state cannot be assured, theradioactive waste 4 can be solidified with glass in the solidifyingvessel 3 and volatilization of theradioactive waste 4 can be suppressed to a lower level. - Glass wool used in the
adiabatic vessel 7 andlid 7A, which are used adiabatic processing in the present embodiment, may be replaced with any one of cellulose fiber, which is a fiber-based adiabatic material, carbonized cork, urethane foam, phenol foam, polystyrene foam, and a potassium silicate board, which is a porous adiabatic material. These adiabatic materials may be used in theadiabatic vessel 7 andlid 7A inembodiments - A radioactive waste solidification method according to
embodiment 2, which is another preferred embodiment of the present invention, will be described with reference toFIGs. 1 and 2 . In the radioactive waste solidification method according to the present embodiment, 100 kg of high-dose radioactive waste that includes 1016 Bq of Sr-90 (for example, spent adsorbents, for radioactive nuclides, the main component of which is a titanate compound to which Sr-90 was adsorbed (the adsorbent will be referred to as the titanate compound adsorbent)) as high-dose radioactive waste and 100 kg of borosilicate glass, which is a glass raw material, with a glass softening point of about 800°C were supplied into a solidifying vessel and a vitrified radioactive waste was produced. The radioactive waste solidification method of the present embodiment will be described below. - In the present embodiment as well, a vitrified
radioactive waste 9 is produced in steps S1, S2, and S3, as inembodiment 1. - In step S1, 100 kg of high-dose
radioactive waste 4, including 1016 Bq of Sr-90, stored in thewaste tank 1 and 100 kg of borosilicate glass, which is glassraw materials 6, stored in the glassraw material tank 1A are supplied into the solidifyingvessel 3. In the present embodiment, theradioactive waste 4 supplied into the solidifyingvessel 3 is a titanate compound adsorbent to which Sr-90 was adsorbed. - After the
radioactive wastes 4 and glassraw materials 6 were supplied into the solidifyingvessel 3, step S2 is executed. That is, as in theembodiment 1, the solidifyingvessel 3 which was filled with theradioactive waste 4 and glassraw materials 6 is disposed in theadiabatic vessel 7, and thelid 7A is attached to theadiabatic vessel 7 to seal it. Radiation emitted by the decay of Sr-90 included in theradioactive waste 4 existing in the solidifyingvessel 3 enclosed with thelid 7A andadiabatic vessel 7 is absorbed by theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 and is then converted to thermal energy. Theradioactive waste 4 and glassraw materials 6 enclosed with thelid 7A andadiabatic vessel 7 are heated due to this thermal energy and their temperatures are raised. The temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 enclosed with thelid 7A andadiabatic vessel 7 become substantially uniform; these temperatures do not become non-uniform depending on the positions of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3. An adiabatic area is formed in the sealedadiabatic vessel 7 as described above. In the present embodiment as well, the solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6 is disposed in this adiabatic area. - For example, Sr-90 emits about 2.8 MeV of energy per disintegration. If this radiation is absorbed in the
radioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, the radiation is converted to thermal energy. Since theradioactive waste 4 includes 1016 Bq of Sr-90, if radiation emitted from each Sr-90 is all absorbed in theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, thermal energy of 2.8 MeV x 1016 Bq (= 2.8E22 eV/s), that is, at a heat generation rate of 4520 J/s, is obtained. If the specific heat of the mixture of the radioactive waste (titanate compound adsorbent to which Sr-90 has been adsorbed) 4 and glass raw material (borosilicate glass) 6 is 0.5 J/(g.K), the temperatures of theradioactive waste 4 and glassraw materials 6 are each raised by about 160°C per hour. Borosilicate glass, which is the glassraw material 6, is melted due to this temperature rise and flows into clearances among theradioactive waste 4. - In step S3, a vitrified
radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through theadiabatic vessel 7 andlid 7A, an actual temperature rise rate in the solidifyingvessel 3 is lower than 160°C/h. However, a temperature rise is continued with time, so all glassraw materials 6 in the solidifyingvessel 3 are melted. As a result, clearances betweenradioactive waste 4 are filled with the molted substances of the glassraw materials 6, and a vitrifiedradioactive waste 9 in which a glass-solidifiedsubstance 8 exists in the solidifyingvessel 3 is produced; in the vitrifiedradioactive waste 9, theradioactive waste 4 have been integrated by the melted substances of the glassraw materials 6. The vitrifiedradioactive waste 9 is taken out of theadiabatic vessel 7 and a lid (not shown) is attached to the solidifyingvessel 3 of the vitrifiedradioactive waste 9 to seal it. Thereafter, the vitrifiedradioactive waste 9 is stored as a waste body at a prescribed storage place (not shown). - The present embodiment can be obtained the effects generated in the
embodiment 1. - As substitute for borosilicate glass, any one of glass raw materials described in
embodiment 1 may be used as the glassraw material 6. In the present embodiment, theradioactive waste 4 solidified with the glassraw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, or insoluble ferrocyanide, besides a titanate compound adsorbent. - A radioactive waste solidification method according to
embodiment 3, which is another preferred embodiment of the present invention, will be described with reference toFIGs. 1 and3 . In the radioactive waste solidification method of the present embodiment, 100 kg of high-dose radioactive waste that include 1015 Bq of Cs-137 (for example, a spent adsorbent, for radioactive nuclides, the main component of which is insoluble ferrocyanide and to which Cs-137 was adsorbed (the adsorbent will be referred to as the insoluble ferrocyanide compound adsorbent)) as high-dose radioactive waste and 100 kg of vanadium-based glass, which is a glass raw material, with a glass softening point of about 300°C were supplied into a solidifying vessel and a vitrified radioactive waste was produced. The radioactive waste solidification method of the present embodiment will be described below. - In the present embodiment as well, a vitrified
radioactive waste 9 is produced in steps S1, S2 and S3, as inembodiment 1. In adiabatic processing in step S2 in the present embodiment, however, a pressure reducing vessel (second vessel) 10 is used instead of theadiabatic vessel 7 used in step S2 inembodiments - In the present embodiment, 100 kg of insoluble ferrocyanide compound adsorbent, which is the
radioactive waste 4 in thewaste tank 1, and 100 kg of vanadium-based glass, which is the glassraw material 6 in the glassraw material tank 1A, are supplied into the solidifying vessel (first vessel) 3 in step S1. The solidifyingvessel 3 into which theradioactive waste 4 and vanadium-based glass were supplied is then disposed in thepressure reducing vessel 10 in step S2. Alid 10A is attached to thepressure reducing vessel 10 to seal it. - An
exhaust pipe 12 connected to thepressure reducing vessel 10 is connected to apressure reducing pump 11. In addition, anexhaust pipe 13 is connected to thepressure reducing pump 11. In step S2, the pressure in the sealedpressure reducing vessel 10 is reduced as described below. - After the
lid 10A is attached to thepressure reducing vessel 10 to seal it, thepressure reducing pump 11 is driven and an opening/closing valve (not shown) attached to theexhaust pipe 12 is opened. When the opening/closing valve is opened, the gas in the sealedpressure reducing vessel 10 in which the solidifyingvessel 3 is disposed is released to the outside through theexhaust pipe 12. This exhaust of the gas by theexhaust pipe 12 is performed until the pressure in thepressure reducing vessel 10 drops to one-tenth the atmospheric pressure. When the pressure in thepressure reducing vessel 10 becomes one-tenth the atmospheric pressure, thepressure reducing pump 11 is stopped and the opening/closing valve attached to theexhaust pipe 12 is closed. When the pressure in the sealedpressure reducing vessel 10, which surrounds the solidifyingvessel 3 filled with the radioactive waste (for example, an insoluble ferrocyanide compound adsorbent) 4 and glass raw materials (vanadium-based glass) 6, is reduced to one-tenth the atmospheric pressure, adiabatic performance is improved by a factor of about 10 as compared with the use of theadiabatic vessel 7. - When the pressure in the sealed
pressure reducing vessel 10 is reduced, an adiabatic area in which the pressure was reduced is formed in thepressure reducing vessel 10. The solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6 is disposed in the adiabatic area in the sealedpressure reducing vessel 10. - When the solidifying
vessel 3 is thermally insulated by pressure reduction as described above, radiation generated due to the decay of Cs-137 included in theradioactive waste 4 in the solidifyingvessel 3 is absorbed by theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 and is then converted to thermal energy. Theradioactive waste 4 and glassraw materials 6 enclosed with thelid 10A andpressure reducing vessel 10 and existing in the area at a reduced pressure (adiabatic area) are heated due to this thermal energy. Accordingly, the temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 are raised. These temperatures become substantially uniform; these temperatures do not become non-uniform depending on the positions of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3. - For example, Cs-137 emits radiation with about 1.15 MeV of energy per disintegration, as described in
embodiment 1. When this radiation is absorbed in theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, the radiation is converted to thermal energy. Since theradioactive waste 4 includes 1015 Bq of Cs-137, if radiation emitted from each Cs-137 is all absorbed in theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, thermal energy of 1.15 MeV x 1015 Bq (= 1.15E21 eV/s), that is, at a heat generation rate of 184 J/s, is obtained. If the specific heat of the mixture of the radioactive waste (an insoluble ferrocyanide compound adsorbent to which Cs-137 was adsorbed) 4 and glass raw material (vanadium-based glass) 6 is 0.5 J/(g.K), the temperatures of theradioactive waste 4 and glassraw materials 6 are each raised by about 6.6°C per hour. - In step S3, a vitrified
radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through theadiabatic vessel 7 andlid 7A, an actual temperature rise rate in the solidifyingvessel 3 is lower than 6.6°C/h. However, a temperature rise is continued with time, so all glassraw materials 6 in the solidifyingvessel 3 are melted. As a result, clearances betweenradioactive waste 4 are filled with the molted substances of the glassraw materials 6, and a vitrifiedradioactive waste 9 in which a glass-solidifiedsubstance 8 exists in the solidifyingvessel 3 is produced; in the vitrifiedradioactive waste 9, theradioactive waste 4 have been integrated by the melted substances of the glassraw materials 6. The vitrifiedradioactive waste 9 is taken out of thepressure reducing vessel 10 and a lid (not shown) is attached to the solidifyingvessel 3 of the vitrifiedradioactive waste 9 to seal it. Thereafter, the vitrifiedradioactive waste 9 is stored as a waste body at a prescribed storage place (not shown). - The present embodiment can be obtained the effects generated in the
embodiment 1. Particularly, in the present embodiment, theradioactive waste 4 and glassraw materials 6 existing in the adiabatic area in the sealedpressure reducing vessel 10 are uniformly heated, so the temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 become more uniform. Furthermore, in the present embodiment, the solidifyingvessel 3 including theradioactive waste 4 and glassraw materials 6 is disposed in the sealedpressure reducing vessel 10 and the pressure in thepressure reducing vessel 10 is reduced, so a desired adiabatic effect can be obtained by adjusting the degree of pressure reduction. - As substitute for vanadium-based glass, any one of the glasses described in
embodiment 1 may be used as the glassraw material 6. In the present embodiment, theradioactive waste 4 solidified with the glassraw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, or a titanate compound, besides an insoluble ferrocyanide compound adsorbent. - A radioactive waste solidification method according to
embodiment 4, which is another preferred embodiment of the present invention, will be described with reference toFIGs. 1 and4 . In the radioactive waste solidification method of the present embodiment, 100 kg of high-dose radioactive waste that includes 1015 Bq of Co-60 (for example, a solid-state radioactive waste the main component of which is an iron oxide including Co-60 (the radioactive waste will be referred to as the iron oxide)) as high-dose radioactive waste and 100 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel to produce a vitrified radioactive waste. The radioactive waste solidification method of the present embodiment will be described below. - In the present embodiment as well, a vitrified
radioactive waste 9 is produced in steps S1, S2 and S3, as inembodiment 1. In the present embodiment, however, the radioactive waste (for example, iron oxides) 4 and glass raw materials (soda-lime glass) 6 supplied into the solidifyingvessel 3 are mixed with an agitator in step S1 and in adiabatic processing in step S2, theadiabatic vessel 7 to which an air supply pipe that has an air supply pump is connected and further, an exhaust pipe is also connected is used instead of theadiabatic vessel 7 used in step S2 inembodiments - In the present embodiment, 100 kg of iron oxide, which is the
radioactive waste 4 supplied from thewaste tank 1, and 100 kg of soda lime glass, which is the glassraw material 6 supplied from the glassraw material tank 1A, are supplied into the solidifyingvessel 3 in step S1. After that, an agitator 14 is inserted into the solidifyingvessel 3 in step S1. Theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 are mixed with this agitator 14. - Upon completion of the mixing of the
radioactive waste 4 and glassraw materials 6, the solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6 is disposed in theadiabatic vessel 7 in step S2. Thelid 7A is attached to theadiabatic vessel 7 to seal it. Anair supply pipe 17 to which anair supply pump 16 and an opening/closing valve (not shown) are attached and anexhaust pipe 18 to which an opening/closing valve (not shown) is attached are connected to theadiabatic vessel 7. Athermometer 19 is attached to theadiabatic vessel 7. - In a state in which the
adiabatic vessel 7 is sealed, adiabatic processing in step S2 is performed for the solidifyingvessel 3 filled with theradioactive waste 4 and glassraw materials 6. Radiation emitted by the decay of Co-60 included in theradioactive waste 4 existing in the solidifyingvessel 3 enclosed with the sealedadiabatic vessel 7 is absorbed by theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 and is then converted to thermal energy. Theradioactive waste 4 and glassraw materials 6 enclosed with thelid 7A andadiabatic vessel 7 are heated due to this thermal energy and their temperatures are raised. The temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 enclosed with thelid 7A andadiabatic vessel 7 become substantially uniform; these temperatures do not become non-uniform depending on the positions of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3. - For example, Co-60 emits radiation with about 2.5 MeV of energy per disintegration. When this radiation is absorbed in the
radioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, the radiation is converted to thermal energy. Since theradioactive waste 4 includes 1015 Bq of Co-60, if radiation emitted from each Co-60 is all absorbed in theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, thermal energy of 2.5 MeV x 1015 Bq (= 2.5 E22 eV/s), that is, at a heat generation rate of 4000 J/s, is obtained. If the specific heat of the mixture of the radioactive waste (iron oxide including Co-60) 4 and glass raw material (soda lime glass) 6 is 0.5 J/(g.K), the temperatures of theradioactive waste 4 and glassraw materials 6 are each raised by about 144°C per hour. - In step S3, a vitrified
radioactive waste 9 is produced. Specifically, since some heat is emitted to the outside through theadiabatic vessel 7 andlid 7A, an actual temperature rise rate in the solidifyingvessel 3 is lower than 144°C/h. However, a temperature rise is continued with time, so all glassraw materials 6 in the solidifyingvessel 3 are melted. At that time, the temperature of the solidifyingvessel 3 in theadiabatic vessel 7 is measured with thethermometer 19. When the temperature of the solidifyingvessel 3 reaches 800°C, which is suitable for the melting of the glass raw materials (soda lime glass) 6, in order to prevent the temperature of the solidifyingvessel 3 from being further raised, the opening/closing valve attached to theair supply pipe 17 and the opening/closing valve attached to theexhaust pipe 18 are opened and theair supply pump 16 is driven. As the result, an external gas (air) is supplied into the interior of theadiabatic vessel 7 through theair supply pipe 17 and the temperature of the solidifyingvessel 3 is maintained at an appropriate temperature. The air supplied into theadiabatic vessel 7 is exhausted to the outside of theadiabatic vessel 7 through theexhaust pipe 18. The amount of air to be supplied into theadiabatic vessel 7 according to the temperature of the solidifyingvessel 3 can be adjusted by controlling the rotational speed of theair supply pump 16. - As a result, clearances between the
radioactive waste 4 are filled with the molted substances of the glassraw materials 6, and a vitrifiedradioactive waste 9 in which a glass-solidifiedsubstance 8 exists in the solidifyingvessel 3 is produced; in the vitrifiedradioactive waste 9, theradioactive waste 4 have been integrated by the melted substances of the glassraw materials 6. The vitrifiedradioactive waste 9 is taken out of theadiabatic vessel 7 and a lid (not shown) is attached to the solidifyingvessel 3 of the vitrifiedradioactive waste 9 to seal it. Thereafter, the vitrifiedradioactive waste 9 is stored as a waste body at a prescribed storage place (not shown). - The present embodiment can be obtained the effects generated in the
embodiment 1. In the present embodiment, since theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 are mixed with the agitator 14, a uniform vitrifiedradioactive waste 9 can be produced in a shorter time. In addition, in the present embodiment, the amount of gas (for example, air) to be supplied into theadiabatic vessel 7 is adjusted based on the measured temperature of the solidifyingvessel 3 in theadiabatic vessel 7, so that it is possible to prevent the temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, which are raised by heat generated due to the decay of radioactive nuclides (for example, Co-60), from exceeding a temperature necessary for glass solidification. Therefore, the evaporation of radioactive nuclides included in theradioactive waste 4 can be suppressed. - During solidification with the molted glass
raw materials 6 as well, the amount of gas to be supplied into theadiabatic vessel 7 can also be adjusted based on the measured temperature of the solidifyingvessel 3. Since the temperature during solidification with glass is measured and the amount of gas to be supplied is controlled, the rate at which the glassraw materials 6 are cooled can be adjusted. This can suppress the vitrifiedradioactive waste 9 from being cracked due to thermal distortion. - As substitute for soda lime glass, any one of the glasses described in
embodiment 1 may be used as the glassraw materials 6. In the present embodiment, theradioactive waste 4 solidified with the glassraw material 6 may be zeolite, clinoptilolite, mordenitem, chabazite, an insoluble ferrocyanide compound, or a titanate compound, besides iron oxides. - A radioactive waste solidification method according to
embodiment 5, which is another preferred embodiment of the present invention, will be described with reference toFIG. 5 . In the radioactive waste solidification method according to the present embodiment, 100 kg of high-dose radioactive waste that includes 1016 Bq of Cs-137 (for example, zeolite to which Cs-137 was adsorbed) as high-dose radioactive waste and 300 kg of soda lime glass, which is a glass raw material, with a glass softening point of about 700°C were supplied into a solidifying vessel to produce a vitrified radioactive waste. The radioactive waste solidification method of the present embodiment will be described below. - In the present embodiment as well, a vitrified
radioactive waste 9 is produced in steps S1, S2 and S3, as inembodiment 1. In the present embodiment, however, theradioactive waste 4 and glassraw materials 6 are supplied into the solidifyingvessel 3 at the same time in step S1 and, in adiabatic processing in step S2, thepressure reducing vessel 10 is used as inembodiment 1. - In the present embodiment, 100 kg of high-dose
radioactive waste 4, including 1016 Bq of Cs-137, supplied from thewaste tank 1 and 300 kg of glassraw material 6 supplied from the glassraw material tank 1A are supplied into the solidifyingvessel 3 at the same time in step S1. Theradioactive waste 4 is spent adsorbent the main component of which is insoluble ferrocyanide and to which Cs-137 was adsorbed. The glassraw material 6 is soda lime glass. Theradioactive waste 4 and glassraw materials 6 are mixed in the solidifyingvessel 3. For convenience, the mixedradioactive waste 4 and glassraw materials 6 will be referred to as themixed filler 15. - The solidifying
vessel 3 filled with themixed filler 15 is disposed in thepressure reducing vessel 10 in step S2, as inembodiment 3. Thethermometer 19 is attached to thepressure reducing vessel 10. Thelid 10A is attached to thepressure reducing vessel 10 to seal it. After that, thepressure reducing pump 11 is driven and the pressure in the sealedpressure reducing vessel 10 is reduced to one-tenth the atmospheric pressure, as inembodiment 3. - In a state in which the solidifying
vessel 3 filled with theradioactive waste 4 and glassraw materials 6 is enclosed with thelid 10A andpressure reducing vessel 10 and disposed in the decompressed atmosphere in thepressure reducing vessel 10 the pressure in which was reduced, theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3 are heated by thermal energy generated due to the decay of Cs-137 included in theradioactive waste 4. The temperatures of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3, which is thermally insulated from the outside, are thereby raised. These temperatures become substantially uniform; these temperatures do not become non-uniform depending on the positions of theradioactive waste 4 and glassraw materials 6 in the solidifyingvessel 3. - When this state is maintained, the glass
raw materials 6 in the solidifyingvessel 3 are melted and this molted glassraw materials 6 osmoses clearances among theradioactive waste 4. When the temperature of the solidifyingvessel 3, which is measured with thethermometer 19, is raised to a temperature suitable for the melting of the glassraw materials 6, in order to prevent the temperature of the solidifyingvessel 3, that is, the temperatures of the glassraw materials 6 from being further raised beyond the temperature suitable for the melting, the pressure in thepressure reducing vessel 10 is controlled by supplying air to and exhausting air from thepressure reducing vessel 10 with thepressure reducing pump 11. As a result, the temperatures of the glassraw materials 6 are maintained at an appropriate temperature. - For example, Cs-137 emits radiation with about 1.15 MeV of energy per disintegration, as described above. Therefore, when the
radioactive waste 4 includes 1016 Bq of Cs-137, thermal energy at a heat generation rate of 1840 J/s is obtained. If the specific heat of the mixture of the radioactive waste (zeolite to which Cs-137 was adsorbed) 4 and glass raw material (soda lime glass) 6 is 0.5 J/(g.K), the temperatures of theradioactive waste 4 and glassraw materials 6 are each raised by about 33°C per hour. - In step S3, a vitrified
radioactive waste 9 is produced. Specifically, a temperature rise is continued with time, so all glassraw materials 6 are melted. As a result, clearances betweenradioactive waste 4 are filled with the molted substances of the glassraw materials 6, and a vitrifiedradioactive waste 9 in which a glass-solidifiedsubstance 8 exists in the solidifyingvessel 3 is produced; in the vitrifiedradioactive waste 9, theradioactive waste 4 have been integrated by the melted substances of the glassraw materials 6. The vitrifiedradioactive waste 9 is taken out of thepressure reducing vessel 10 and a lid (not shown) is attached to the solidifyingvessel 3 of the vitrifiedradioactive waste 9 to seal it. Thereafter, the vitrifiedradioactive waste 9 is stored as a waste body at a prescribed storage place (not shown). - The present embodiment can be obtained the effects generated in the
embodiment 3. Furthermore, in the present embodiment, since the state of reduction in pressure in thepressure reducing vessel 10 is controlled based on the temperature of the solidifyingvessel 3 that is measured during solidification with glass, temperature in solidification with glass can be controlled to a desired value. Furthermore, it becomes also possible to suppress the vitrifiedradioactive waste 9 from being cracked due to thermal distortion because cooling temperature after glass has been molted is controlled. - As substitute for soda lime glass, any one of the glasses described in the first embodiment may be used as the glass
raw materials 6. In the present embodiment, theradioactive waste 4 solidified with the glassraw material 6 may be clinoptilolite, mordenitem, chabazite, an insoluble ferrocyanide compound, or a titanate compound, besides zeolite. -
- 1 : waste tank, 1A : glass raw material tank, 3 : solidifying vessel (first vessel), 4 : radioactive waste, 6 : glass raw materials, 7 : adiabatic vessel (second vessel), 8 : glass-solidified substance, 10 : pressure reducing vessel (second vessel), 11 : pressure reducing pump, 14 : agitator, 16 : air supply pump, 19 : thermometer.
Claims (5)
- A radioactive waste solidification method comprising steps of:supplying radioactive waste including radioactive nuclides and glass raw materials into a first vessel (3) ;disposing the first vessel (3) in which the radioactive waste and glass raw materials (1A) exist, in an adiabatic area in a second vessel (7);heating the radioactive waste and glass raw materials (1A) in the first vessel (3) existing in the adiabatic area in the second vessel (7) by heat generated by radiation emitted from the radioactive nuclides; andproducing a vitrified radioactive waste by melt of the heated glass raw materials.
- The radioactive waste solidification method according to claim 1, wherein in the disposition of the first vessel (3), in which the radioactive waste and the glass raw material exist, into the adiabatic area, the first vessel (3) is disposed in an adiabatic area formed in an adiabatic vessel being the second vessel (7).
- The radioactive waste solidification method according to claim 1, wherein in the disposition of the first vessel (3), in which the radioactive waste and the glass raw material exist, into the adiabatic area, the first vessel (3) is disposed in a pressure reducing vessel (10) being the second vessel, and a pressure in a space in which the first vessel (3) is disposed is reduced to form the adiabatic area, the space being in the pressure reducing vessel (10).
- The radioactive waste solidification method according to any one of claims 1 to 3, wherein a temperature of the first vessel (3) disposed in the adiabatic area in the second vessel is measured, and a flow rate of a gas supplied to the adiabatic area in the second vessel is adjusted based on the measured temperature.
- The radioactive waste solidification method according to claim 1 or 3, wherein a temperature of the first vessel (3) disposed in the adiabatic area in the second vessel is measured, and a pressure in the adiabatic area in the second vessel is controlled.
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JP2014052245A JP6126031B2 (en) | 2014-03-14 | 2014-03-14 | Solidification method for radioactive waste |
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JP6423194B2 (en) * | 2014-07-23 | 2018-11-14 | 日立Geニュークリア・エナジー株式会社 | Solidification method for radioactive waste |
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US3365578A (en) * | 1962-08-10 | 1968-01-23 | Atomic Energy Authority Uk | Glass composition comprising radioactive waste oxide material contained within a steel vessel |
US4351749A (en) * | 1978-11-18 | 1982-09-28 | Vitrex Corporation | Molecular glasses for nuclear waste encapsulation |
JPS6013295A (en) * | 1983-07-04 | 1985-01-23 | 株式会社東芝 | Method of solidifying and treating radioactive waste |
JPS62124499A (en) | 1985-11-26 | 1987-06-05 | 株式会社東芝 | Method of solidifying and processing radioactive waste |
JPS62165198A (en) * | 1986-01-17 | 1987-07-21 | 株式会社新来島どっく | Hydrothermal solidifying processing method of high-level radioactive waste |
JP4772459B2 (en) | 2005-11-10 | 2011-09-14 | 株式会社東芝 | Solidification method for radioactive waste |
WO2007134159A2 (en) * | 2006-05-10 | 2007-11-22 | Massachusetts Institute Of Technology | Directed energy melter |
JP5472704B2 (en) | 2009-08-26 | 2014-04-16 | 三菱マテリアル株式会社 | Co-based alloy member for electric melting furnace and electric melting furnace for high-level radioactive waste vitrification treatment |
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