EP0155418A2 - Verfahren zur Beseitigung von radioaktiven Abfällen durch Volumenverminderung - Google Patents

Verfahren zur Beseitigung von radioaktiven Abfällen durch Volumenverminderung Download PDF

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Publication number
EP0155418A2
EP0155418A2 EP84303715A EP84303715A EP0155418A2 EP 0155418 A2 EP0155418 A2 EP 0155418A2 EP 84303715 A EP84303715 A EP 84303715A EP 84303715 A EP84303715 A EP 84303715A EP 0155418 A2 EP0155418 A2 EP 0155418A2
Authority
EP
European Patent Office
Prior art keywords
waste
product
radioactive
glass fibers
incineration
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
EP84303715A
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English (en)
French (fr)
Other versions
EP0155418A3 (de
Inventor
Koei C/O Mitsubishi Jukogyo K. K. Sato
Noriyuki C/O Mitsubishi Jukogyo K. K. Yamauchi
Toshihiko C/O Mitsubishi Jukogyo K. K. Hirayama
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Publication of EP0155418A2 publication Critical patent/EP0155418A2/de
Publication of EP0155418A3 publication Critical patent/EP0155418A3/de
Withdrawn legal-status Critical Current

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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
    • G21F9/308—Processing by melting the waste

Definitions

  • This invention is concerned with a method, involving volume reduction, for disposal of radioactive waste such as is generated from a radioactive material handling installation, for example a nuclear power station.
  • atomic energy installations such as nuclear power stations, are known to generate radioactive waste liquid, combustible solid wastes (combustible miscellaneous solids such as clothes, paper and wood, active carbon or similar materials used in air-conditioning systems, used ion exchange resin and waste oil, and non-combustible solid wastes (for example, glass wool and metallic parts).
  • combustible solid wastes combustible miscellaneous solids such as clothes, paper and wood, active carbon or similar materials used in air-conditioning systems, used ion exchange resin and waste oil
  • non-combustible solid wastes for example, glass wool and metallic parts
  • radioactive waste liquid reduction is achieved by converting it into a sparingly soluble material by chemical reaction and then it is separated by drying or concentration, volatile components being treated by calcination.
  • the precise treatment of such liquids depends upon the precise nature of the liquids themselves. For example in a PWR power station the liquid is mostly liquid containing boric acid used for neutron suppression and in a BWR power station it is mostly whole liquid containing sodium sulphate.
  • Combustible solid wastes such as wood and paper are generally reduced in volume by incineration to yield ash including as principle components silicon oxide and metal oxides. Non-combustible solid wastes are often reduced in volume by compression.
  • glass frit of good quality is needed as a raw material for the solidifying glass. Furthermore, it is necessary to select, as glass frit, material which has been mixed in an optimum proportion depending on the nature of the high-level radioactive waste involved. There is also a problem in that, since glass frit of good quality is conventionally brought for use from outside the atomic energy installation, it is expensive. The use of this frit also obviously increases the volume of the waste.
  • a method of disposal of radioactive atomic energy installation waste products characterised in that a product containing radioactive material and obtained as a result of the treatment, such as by drying, calcination and/or incineration, of radio-active waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radioactive material adherent thereto, and the mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
  • a melting furnace 1 is connected with a container 2 for a product of incineration or the like, through a cutting device 2-1 for the product of incineration or the like, which device is provided with a setter 2-2.
  • the furnace 1 is also connected with containers 3, 4 and 5 for different kinds of waste glass fibers each of which containers is provided with its own cutting device, 3-1, 4-1 and 5-1 respectively, for the waste glass fibers therein.
  • a device 6 for collecting melt discharged from the melting furnace 1 is also provided.
  • the product of incineration or the like comprises ash-like powder, while the waste glass fibers are fiber-like solidified masses.
  • a radioactive waste liquid is calcined for the purpose of volume reduction, it is converted into a composition principally comprising various metal oxides containing non-volatile radioactive materials.
  • a radioactive waste liquid is calcined for the purpose of volume reduction, it is converted into a composition principally comprising various metal oxides containing non-volatile radioactive materials.
  • boric acid B is a principal component
  • Na is a principal component.
  • the both materials, mixed together within the melting furnance 1, are heated to a temperature at which the waste glass fibers melt.
  • metals and metal oxides having higher melting points than that of the waste glass fibers may be present in the form of granular or other particulate solid material in the melt, but combustible materials are burnt, and thereby a glass-like product having a maximum overall rate of volume reduction can be produced.
  • heating is continued to a temperature at which the metals and metal oxides having higher melting points than that of the glass fibers also melt, then the glass fibers and these metals and metal oxides' melt together and become coupled in molecular structures to give a more stable glass-like product.
  • the melt is transferred from the melting furnace 1 to the melt collecting container 6, then it is cooled to yield a solidified mass in which radioactivity, metals, metal oxides and the like are sealed.
  • the melt can be cooled and solidified within the melting furnace 1 without being transferred to the melt collecting container 6, and the material for disposal can be taken out of the furnace 1 in the form of a solidified mass.
  • a preferred mixing proportion between the waste glass wool and the product of incineration or the like is, for example, 20% of A in Table-1 and 80% (wt %) of glass wool. These, are mixed together and heated to about 1,400°C to become molten and yield a product of the following composition:
  • This product on cooling is a solidified mass of the conventional borosilicate glass, and at room temperature it has strength, stablity, durability and exudation- resistance (as represented by the weight of component exuding through a unit area when forced stirring has been effected in distilled hot water at 100°C).
  • the invention can overcome difficulties which arise in connection with the product of incineration or the like which is a pulverized material which is liable to sputter, is hygroscopic, and needs countermeasures to be taken for maintenance and storage, and arising from the relative inefficiency of the known volume reduction by compression of the waste glass fibers.
  • the invention further makes it possible to provide a stable solidified mass which has an extremely small exudation rate of radioactive material and which has appropriate strength and ageing properties.
  • the raw material cost is zero and increase in the amount of waste is avoided.
  • glass is a noncrystalline (amorphous) material, it has a flexibility in that it can enclose foreign materials, such as metal oxides and achieve the required mechanical strength in a range of appropriate amounts rather than in amounts of fixed proportions.
  • a first melting experiment may be carried out in a small crucible as above described and in practice the respective amounts of the wastes described above are suitably determined at such proportions that the entire amounts of such waste glass and treated liquids and solids can be molten together without leaving any excess nor running into shortage, that is, at such proportions that the amounts of the waste materials which are in short supply and hence may have to be brought in from outside of the atomic power .installation can be minimized, preferably can be made zero.
  • Such a trial-and-error experiment will determine the appropriate proportions for each instance.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Processing Of Solid Wastes (AREA)
EP84303715A 1983-12-06 1984-06-04 Verfahren zur Beseitigung von radioaktiven Abfällen durch Volumenverminderung Withdrawn EP0155418A3 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP22909183A JPS60122397A (ja) 1983-12-06 1983-12-06 放射性廃棄物の減容化処理方法
JP229091/83 1983-12-06

Publications (2)

Publication Number Publication Date
EP0155418A2 true EP0155418A2 (de) 1985-09-25
EP0155418A3 EP0155418A3 (de) 1986-11-20

Family

ID=16886606

Family Applications (1)

Application Number Title Priority Date Filing Date
EP84303715A Withdrawn EP0155418A3 (de) 1983-12-06 1984-06-04 Verfahren zur Beseitigung von radioaktiven Abfällen durch Volumenverminderung

Country Status (3)

Country Link
EP (1) EP0155418A3 (de)
JP (1) JPS60122397A (de)
CA (1) CA1230221A (de)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0518090A1 (de) * 1991-06-03 1992-12-16 Siemens Aktiengesellschaft Verfahren und Einrichtung zur Behandlung einer radioaktiven Abfallösung
FR2940718A1 (fr) * 2008-12-30 2010-07-02 Areva Nc Verre alumino-borosilicate pour le confinement d'effluents liquides radioactifs, et procede de traitement d'effluents liquides radioactifs
CN113990544A (zh) * 2021-10-28 2022-01-28 武汉理工大学 一种中低放玻璃纤维与高放废液协同玻璃固化的方法
KR102615509B1 (ko) * 2023-04-05 2023-12-19 (주)한국원자력 엔지니어링 방사성폐기물 고형화 및 고정화 방법

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05249294A (ja) * 1992-03-03 1993-09-28 Nuclear Fuel Ind Ltd 放射能汚染物質の固化廃棄処理方法
FR3009642B1 (fr) * 2013-08-08 2018-11-09 Areva Nc Procede et installation d'incineration, fusion et vitrification de dechets organiques et metalliques

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2731327C3 (de) * 1977-07-12 1981-01-22 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur Filterung von Staub aus radioaktiven Abgasen und Einrichtung zur Durchführung des Verfahrens
DE3110192A1 (de) * 1981-03-17 1982-10-07 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur umhuellung von radioaktiv kontaminierten oder radioaktive stoffe enthaltenden feststoffen aus kerntechnischen anlagen mit einer endlagerfaehigen matrix
DE3142356A1 (de) * 1981-10-26 1983-05-11 Alkem Gmbh, 6450 Hanau "verfahren zum endkonditionieren von radioaktivem und/oder toxischem abfall"

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0518090A1 (de) * 1991-06-03 1992-12-16 Siemens Aktiengesellschaft Verfahren und Einrichtung zur Behandlung einer radioaktiven Abfallösung
FR2940718A1 (fr) * 2008-12-30 2010-07-02 Areva Nc Verre alumino-borosilicate pour le confinement d'effluents liquides radioactifs, et procede de traitement d'effluents liquides radioactifs
WO2010076288A3 (fr) * 2008-12-30 2010-08-26 Areva Nc Verre alumino-borosilicaté pour le confinement d'effluents liquides radioactifs, et procédé de traitement d'effluents liquides radioactifs
CN102272859A (zh) * 2008-12-30 2011-12-07 阿雷瓦核废料回收公司 用于密封放射性废液的铝硼硅酸盐玻璃、以及处理放射性废液的方法
RU2523715C2 (ru) * 2008-12-30 2014-07-20 Арева Нс Алюмоборосиликатное стекло для изоляции радиоактивных жидких эфлюентов и способ обработки радиоактивных жидких эфлюентов
CN102272859B (zh) * 2008-12-30 2015-04-08 阿雷瓦核废料回收公司 用于密封放射性废液的铝硼硅酸盐玻璃、以及处理放射性废液的方法
US9029278B2 (en) 2008-12-30 2015-05-12 Areva Nc Alumino-borosilicate glass for the confinement of radioactive liquid effluents, and method for treating radioactive liquid effluents
CN113990544A (zh) * 2021-10-28 2022-01-28 武汉理工大学 一种中低放玻璃纤维与高放废液协同玻璃固化的方法
KR102615509B1 (ko) * 2023-04-05 2023-12-19 (주)한국원자력 엔지니어링 방사성폐기물 고형화 및 고정화 방법

Also Published As

Publication number Publication date
CA1230221A (en) 1987-12-15
JPS60122397A (ja) 1985-06-29
EP0155418A3 (de) 1986-11-20

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Inventor name: SATO, KOEIC/O MITSUBISHI JUKOGYO K. K.

Inventor name: YAMAUCHI, NORIYUKIC/O MITSUBISHI JUKOGYO K. K.

Inventor name: HIRAYAMA, TOSHIHIKOC/O MITSUBISHI JUKOGYO K. K.