WO1985001828A1 - Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium - Google Patents

Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium Download PDF

Info

Publication number
WO1985001828A1
WO1985001828A1 PCT/US1983/001626 US8301626W WO8501828A1 WO 1985001828 A1 WO1985001828 A1 WO 1985001828A1 US 8301626 W US8301626 W US 8301626W WO 8501828 A1 WO8501828 A1 WO 8501828A1
Authority
WO
WIPO (PCT)
Prior art keywords
waste
boric acid
magnesium
cement
magnesium oxide
Prior art date
Application number
PCT/US1983/001626
Other languages
English (en)
Inventor
John E. Carlson
Original Assignee
Chem-Nuclear Systems, Inc.
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 Chem-Nuclear Systems, Inc. filed Critical Chem-Nuclear Systems, Inc.
Priority to PCT/US1983/001626 priority Critical patent/WO1985001828A1/fr
Priority to EP83903692A priority patent/EP0157771A1/fr
Priority to JP58503726A priority patent/JPS61500455A/ja
Priority to ES534913A priority patent/ES8703049A1/es
Priority to IT2294984A priority patent/IT1196276B/it
Publication of WO1985001828A1 publication Critical patent/WO1985001828A1/fr

Links

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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
    • C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
    • C04B28/04—Portland cements
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
    • C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
    • C04B2111/00767—Uses not provided for elsewhere in C04B2111/00 for waste stabilisation purposes
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies
    • Y02W30/91—Use of waste materials as fillers for mortars or concrete

Definitions

  • the invention relates to the treatment and disposal of boron containing radioactive waste waters such as characteristically generated by pressurized water reactor (PWR) nuclear facilities. More specifically, the invention relates to the treatment of such wastes in order to convert the same to a form more suitable for handling and disposal by encapsulation in solid binder materials.
  • PWR pressurized water reactor
  • boric acid waste common to pressurized water reactors contains boric acid as a chemical shim for
  • the present invention relates to direct solidification of hot boric acid solutions by specific addition of magnesium compounds to form magnesium borates, which, after the addition of cement, then complexes with added calcium hydroxide or calcium oxide (lime) so that a uniform solid is produced with no apparent free liquid.
  • Aqueous boric acid solutions from pressurized water reactors are mixed with finely powdered magnesium oxide or hydroxide to form a magnesium borate complex. While various powdered magnesium oxides or hydroxides may be utilized, the selection of materials is critical with respect to particle size.
  • a particularly effective magnesium oxide powder is Magox 98 HR manufactured by Basic Chemicals. The fineness of this material is such that 99.5 percent will pass through
  • the temperature of the aqueous boric acid waste is typically 77 degrees Centigrade when it leaves the reactor and is placed into the liner (container). However, this process will work with boric acid materials at .a temperature of 55-95 degrees Centigrade.
  • the magnesium oxide compound is added to the boric acid waste and is continously agitated, in fact, agitation is maintained throughout the entire process until, because of increases in viscosity, agitation is no longer possible or required.
  • the formation of the magnesium borates produces an exotherm which can be monitored by the use of a temperature sensing probe in the container.
  • the exotherm is typically 3-6 degrees Centigrade.
  • the amount of magnesium oxide or hydroxide required to treat each portion of waste is predetermined in the laboratory using process control procedures.
  • the amount of the magnesium compound added is a function, obviously, of the concentration of the boric acid contained in the waste material.
  • the amount of magnesium oxide or hydroxide added is about 50 percent or more by weight of the amount of boric acid (H ⁇ o ) present.
  • cement is added to the liner and agitation is continued.
  • the amount of cement added is as low as about 1/2 the weight of the radioactive waste liquid , in the system. While the choice of the type of cement is not necessarily critical, the use of various forms of Portland Cement is preferred.
  • the calcium oxide or calcium hydroxide is added to the container. The addition of the calcium oxide component causes an increase in the pH of the system which promotes the formation of the gel matrix. It is important to note that the magnesium oxide or magnesium hydroxide in themselves will not shift the pH to the gelling range, even if added in excess. This then prevents premature gellation before the proper amount of cement has been added and mixed.
  • the amount of the calcium- hydroxide or calcium oxide added to achieve the desired product gel is about ' 1/4 of the weight of boric acid waste liquid. As set forth above, the amounts of all components to be employed in this process are
  • the state of the matrix gel formation can be monitored 0 by various means. Usually, the change in viscosity can be seen by an increase in hydraulic pressure for the agitator drive employed for mixing purposes.
  • the gel structure itself has a substantial degree of ⁇ -* rigidity, as shown in the laboratory, even without the addition of cement. It is significant that the boric acid in the waste becomes an integral part of the gel structure, which in combination with the hydrated cement produces a uniform waste matrix. 0
  • the rate at which the cement present in the system exothermically hydrates can be measured by the same probe used to measure the magnesium borate reaction exotherm.
  • the solidified waste material is sufficiently 5 firm for shipment within about 24 hours. It is important that the calcium oxide or hydroxide be added only after the addition of the cement, because the change in pH resulting from the addition of the calcium component will cause the production of a gel and possibly not allow for adequate 0 mixing of the .cement.
  • the instant invention can be utilized for certain wastes produced from boiling water reactors.
  • a radioactive sulfate waste is produced from a boiling water reactor. In such a system it is necessary to
  • magnesium oxides or magnesium hydroxides are both suitable for use, magnesium oxide is preferred because of the reduced cost and weight of the material.
  • the instant invention provides several advantages over other processes for waste disposal.
  • Of principal import is the fact that the amount of cement used in the process can be reduced by up to 50 percent. This allows for a considerably greater amount of room in the
  • the final product contains no free liquids. In the event that there is some unreacted liquid, the liquid will, because of the greater density of the solid product, rise to the top of the container. Additional cement can then be added to solidify
  • a typical liner for radioactive waste disposal contains 5.52 cubic meters of storage space. With prior art 35 processes, only about 3.40 cubic meters of waste could be 1 processed. By the process of this invention, up to 3.96 cubic meters of waste can be effectively solidified in the same size liner.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Ceramic Engineering (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Materials Engineering (AREA)
  • Structural Engineering (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

Des structures en colloïde gélifié (gel) ferme sont formées à partir de solutions aqueuses chaudes de déchets radioactifs contenant de l'acide borique en ajoutant de l'hydroxyde de magnésium ou de l'oxyde de magnésium en poudre et ensuite de l'oxyde de calcium (chaux vive) ou de l'hydroxyde de calcium. Du ciment peut être introduit après addition du composé de magnésium sans interférer avec les réactions successives du gel. La rigidité conférée au produit par le gel permet de réduire de 50 % ou davantage l'utilisation courante de ciment dans le traitement de concentrés radioactifs de l'acide borique. Cela se traduit par une augmentation de la quantité de déchets pouvant être solidifiée par conteneur, par une diminution des réactions exothermiques, par un meilleur rendement lors du transport et un accroissement de la résistance aux fuites de fluides aqueux contenant des nucléides radioactifs.
PCT/US1983/001626 1983-10-17 1983-10-17 Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium WO1985001828A1 (fr)

Priority Applications (5)

Application Number Priority Date Filing Date Title
PCT/US1983/001626 WO1985001828A1 (fr) 1983-10-17 1983-10-17 Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium
EP83903692A EP0157771A1 (fr) 1983-10-17 1983-10-17 Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium
JP58503726A JPS61500455A (ja) 1983-10-17 1983-10-17 酸化マグネシウムの不溶性化合物を用いて水性放射性廃棄物を固化する方法
ES534913A ES8703049A1 (es) 1983-10-17 1984-08-06 Un procedimiento para tratar residuos radiactivos
IT2294984A IT1196276B (it) 1983-10-17 1984-10-02 Solidificazione migliorata di un prodotto di scarto radioattivo acquoso impiegando composti insolubili di ossido di magnesio

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/US1983/001626 WO1985001828A1 (fr) 1983-10-17 1983-10-17 Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium

Publications (1)

Publication Number Publication Date
WO1985001828A1 true WO1985001828A1 (fr) 1985-04-25

Family

ID=22175503

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/US1983/001626 WO1985001828A1 (fr) 1983-10-17 1983-10-17 Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium

Country Status (4)

Country Link
EP (1) EP0157771A1 (fr)
JP (1) JPS61500455A (fr)
IT (1) IT1196276B (fr)
WO (1) WO1985001828A1 (fr)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11392568B2 (en) 2015-06-23 2022-07-19 Microsoft Technology Licensing, Llc Reducing matching documents for a search query
US10229143B2 (en) 2015-06-23 2019-03-12 Microsoft Technology Licensing, Llc Storage and retrieval of data from a bit vector search index
US10467215B2 (en) 2015-06-23 2019-11-05 Microsoft Technology Licensing, Llc Matching documents using a bit vector search index
US11281639B2 (en) 2015-06-23 2022-03-22 Microsoft Technology Licensing, Llc Match fix-up to remove matching documents
US10733164B2 (en) 2015-06-23 2020-08-04 Microsoft Technology Licensing, Llc Updating a bit vector search index
US10565198B2 (en) 2015-06-23 2020-02-18 Microsoft Technology Licensing, Llc Bit vector search index using shards
US10242071B2 (en) 2015-06-23 2019-03-26 Microsoft Technology Licensing, Llc Preliminary ranker for scoring matching documents

Citations (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3126352A (en) * 1958-12-31 1964-03-24 Certificate of correction
US3196619A (en) * 1961-04-19 1965-07-27 Continental Oil Co Method for disposing of harmful organic waste materials
US3837872A (en) * 1970-01-08 1974-09-24 Chemfix Inc Method of making wastes non-polluting and disposable
JPS49104100A (fr) * 1973-02-12 1974-10-02
US4086325A (en) * 1976-02-13 1978-04-25 Belgonucleaire, S.A. Process for drying solutions containing boric acid
US4122028A (en) * 1976-01-28 1978-10-24 Nukem Nuklear-Chemie Und Metallurgie Gmbh Process for solidifying and eliminating radioactive borate containing liquids
GB2032165A (en) * 1978-09-29 1980-04-30 Kernforschungsanlage Juelich Disposal of Tritium-containing Effluents by Solidifciation
JPS5614195A (en) * 1979-07-17 1981-02-10 Japan Gasoline Method of improving waterrresistance of radioactive waste asphalttsolidified body
JPS5620519A (en) * 1979-07-30 1981-02-26 Green Cross Corp:The Recovery of interferon
JPS5620520A (en) * 1979-07-30 1981-02-26 Green Cross Corp:The Recovery of interferon
US4269706A (en) * 1977-06-02 1981-05-26 Reaktor-Brennelment Union Gmbh Method of decontaminating radioactive process waste waters
EP0054604A2 (fr) * 1980-12-19 1982-06-30 Kernforschungszentrum Karlsruhe Gmbh Procédé de préparation de corps résiduaires solidifiés pour le stockage définitif de déchets radioactifs

Patent Citations (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3126352A (en) * 1958-12-31 1964-03-24 Certificate of correction
US3196619A (en) * 1961-04-19 1965-07-27 Continental Oil Co Method for disposing of harmful organic waste materials
US3837872A (en) * 1970-01-08 1974-09-24 Chemfix Inc Method of making wastes non-polluting and disposable
US3837872B1 (fr) * 1970-01-08 1986-02-25
JPS49104100A (fr) * 1973-02-12 1974-10-02
US4122028A (en) * 1976-01-28 1978-10-24 Nukem Nuklear-Chemie Und Metallurgie Gmbh Process for solidifying and eliminating radioactive borate containing liquids
US4086325A (en) * 1976-02-13 1978-04-25 Belgonucleaire, S.A. Process for drying solutions containing boric acid
US4269706A (en) * 1977-06-02 1981-05-26 Reaktor-Brennelment Union Gmbh Method of decontaminating radioactive process waste waters
GB2032165A (en) * 1978-09-29 1980-04-30 Kernforschungsanlage Juelich Disposal of Tritium-containing Effluents by Solidifciation
JPS5614195A (en) * 1979-07-17 1981-02-10 Japan Gasoline Method of improving waterrresistance of radioactive waste asphalttsolidified body
JPS5620520A (en) * 1979-07-30 1981-02-26 Green Cross Corp:The Recovery of interferon
JPS5620519A (en) * 1979-07-30 1981-02-26 Green Cross Corp:The Recovery of interferon
EP0054604A2 (fr) * 1980-12-19 1982-06-30 Kernforschungszentrum Karlsruhe Gmbh Procédé de préparation de corps résiduaires solidifiés pour le stockage définitif de déchets radioactifs

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
CHEMICAL ABSTRACTS 92:81748z. published 3 March 1980. page 342. *

Also Published As

Publication number Publication date
EP0157771A1 (fr) 1985-10-16
JPS61500455A (ja) 1986-03-13
IT8422949A1 (it) 1986-04-02
IT8422949A0 (it) 1984-10-02
IT1196276B (it) 1988-11-16

Similar Documents

Publication Publication Date Title
US4620947A (en) Solidification of aqueous radioactive waste using insoluble compounds of magnesium oxide
US3988258A (en) Radwaste disposal by incorporation in matrix
US4530723A (en) Encapsulation of ion exchange resins
US5678234A (en) Process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes
JPS6233560B2 (fr)
US4671897A (en) Process and apparatus for solidification of radioactive waste
US5732363A (en) Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product
EP0124966B1 (fr) Procédé pour encapsuler des boues dans le ciment
JPH0631850B2 (ja) 放射性廃液の処理処分方法
US5457262A (en) Preparation of inorganic hardenable slurry and method for solidifying wastes with the same
CA2161402A1 (fr) Agent solidifiant pour dechets radioactifs, procede de solidification connexe et produits solidifies obtenus
WO1985001828A1 (fr) Solidification amelioree de dechets radioactifs aqueux par l'utilisation de composes insolubles de l'oxyde de magnesium
US4424148A (en) Process for preparing wastes for non-pollutant disposal
CN1119820C (zh) 一种处理放射性废物的类玻璃体固化材料及固化方法
US4533395A (en) Method of making a leach resistant fixation product of harmful water-containing waste and cement
JP3809045B2 (ja) 沸騰水型原子力発電所から生じた低レベル放射性湿潤廃棄物の共固化方法
JPS5815000B2 (ja) 放射性廃棄物処理方法
EP1137014B1 (fr) Procédé pour la co-solidification de déchets humides faiblement radioactifs issus de réacteurs nucléaires à eau bouillante
Christensen Leaching of cesium from cement solidified BWR and PWR bead resins
JPS623698A (ja) 放射性廃棄物の固化処理方法
JPS6186692A (ja) 使用済放射性イオン交換樹脂の固化方法
Curtiss et al. Radwaste disposal by incorporation in matrix
CA1205097A (fr) Procede de preparation des dechets en vue d'une elimination non polluante
RU2131628C1 (ru) Способ переработки радиоактивных отходов щелочных металлов
JPS6056299A (ja) 粒状放射性廃棄物の固化方法

Legal Events

Date Code Title Description
AK Designated states

Designated state(s): AU BR DK FI JP MC NO SU US

AL Designated countries for regional patents

Designated state(s): AT BE CH DE FR GB LU NL SE