[go: up one dir, main page]

GB2049261A - Method of disposal of tritium- containing water wastes - Google Patents

Method of disposal of tritium- containing water wastes Download PDF

Info

Publication number
GB2049261A
GB2049261A GB8013241A GB8013241A GB2049261A GB 2049261 A GB2049261 A GB 2049261A GB 8013241 A GB8013241 A GB 8013241A GB 8013241 A GB8013241 A GB 8013241A GB 2049261 A GB2049261 A GB 2049261A
Authority
GB
United Kingdom
Prior art keywords
water
cement
tritium
packaging
bentonite
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.)
Granted
Application number
GB8013241A
Other versions
GB2049261B (en
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.)
Karlsruher Institut fuer Technologie KIT
Original Assignee
Kernforschungszentrum Karlsruhe GmbH
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 Kernforschungszentrum Karlsruhe GmbH filed Critical Kernforschungszentrum Karlsruhe GmbH
Publication of GB2049261A publication Critical patent/GB2049261A/en
Application granted granted Critical
Publication of GB2049261B publication Critical patent/GB2049261B/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/16Processing by fixation in stable solid media
    • G21F9/162Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • G21F9/165Cement or cement-like matrix

Landscapes

  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Curing Cements, Concrete, And Artificial Stone (AREA)
  • Processing Of Solid Wastes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)

Abstract

A method of disposing of tritium- containing aqueous wastes in which the wastes are mixed with a bentonite, cement or a cement-sand mixture added to act as a bonding agent, the still liquid cement mix packaged in a suitable material and allowed to set, the packaged material then being suitable for sinking into the sea. The bentonite may be mixed first either with the tritium- containing wastes, or with the cement or cement-sand mixture. The third component is then added. Values are given for the relative ratios of the various components for the two methods.

Description

SPECIFICATION Method of disposal of tritium-containing water wastes The present invention relates to a method of preparing tritium-containing water wastes for sinking into the sea, in which the HTO-containing water wastes are mixed with an inorganic bonding agent, the mixture thus produced being packaged and being allowed to set in the packaging, the solidified product, together with the packaging, then being suitable for sinking into the sea.
It is well known to dispose of radioactive tritium in the form of HTO-containing water wastes by solidifying the wastes with an inorganic bonding agent such as cement and then sinking it into the sea. For this purpose tritium containing effluents have to be fixed and packaged. No demands are made as to the quality of the fixing and packaging.
The transport and container costs for such a method of disposal are very high. Accordingly, it is extremely desirable that the packaging material, usually a drum, contains as high as possible percentage water (and hence tritium) content. Prior art methods accordingly require the mixing water and cement in a weight ratio of from 0.35:1 to 0.8:1. There are thus obtained cement blocks which have a water content of from 50% to 70% by volume. A higher water content cannot be obtained utilising such method because the cement settles out and the water located thereabove remains in a liquid state.
The present invention seeks to provide a method by means of which a higher HTO content in the end product compared with known methods can be obtained. The invention also seeks to provide a method in which expense and costs of transportation of such solidified products are reduced.
In accordance with the present invention, there is provided a method of disposal of tritiumcontaining water wastes in which the HTO-containing water wastes are mixed with an inorganic bonding agent, the mixture then being packaged and allowed to set in the packaging, the solidification product and the packaging then being suitable for sinking into the sea, comprising the steps of mixing tritium-water or water containing synthetic radionuclides and tritium water with a bentonite which is capable of swelling and is water absorbent, the weight ratio of water to bentonite lying with the range of 10:1 to 4:1, adding cement or a cement and sand mixture to the bentonite-water mixture in a ratio by weight which is not less than 1::5 so as to produce a mortar which sets to a cement stone or concrete having a water-cement value of from 1.0 to 4.0, charging the liquid cement or mortar thus obtained into a plastics material or metalenvelope and allowing the liquid cement or mortar to set in such envelope, the solidified product and packaging being suitable for sinking into the sea.
Also in accordance with the present invention, there is provided a method of disposal of tritium-containing water wastes, in which the HTO-containing water wastes are mixed with an inorganic bonding agent, the mixture then being packaged and allowed to set in the packaging, the solidification product and the packaging then being suitable for sinking into the sea comprising the steps of mixing swellable, water absorbent bentonite with cement in a weight ratio lying in the range of 1 :9 to 1::1 and subsequently adding tritium water or water containing synthetic radionuclides and tritium water in an amount sufficient to produce a watercement value of from 1.0 to 4.0, charging the liquid cement or mortar thus obtained into a plastics material or metal envelope and allowing the liquid cement or mortar to set in such envelope, the solidified product and packaging being suitable for sinking into the sea.
The standards of the International Atomic Energy Authority regarding the tritium-water solidification product are not particularly stringent. It is merely necessary that the product must have a density of at least 1.3 g.cm-3. The density of a mixture of water, cement and clay (bentonite), assuming that water has a density of 1 g.cm-3 and that cement and clay have a density of approximately 3 g.cm-3 may be estimated according to the equation: D = 100/ (Z + T) + W where Z is the percentage of cement, T is the percentage of clay and W is the percentage of water, all percentages being by weight.
To achieve a density of 1.3 g.cm-3, the water to solids ratio must be not more than 1.9. The invention will be further described, by way of illustration only, with reference to the following exemplary experiments: 1. Experiments to in crease the maximum water absorbtion capacity in the solids mixture.
The following table shows the effects on the water absorbtion capacity of Portland cement 350 of the addition of a substantially non-swellable and of a highly swellable bentonite: Bentonite W/Z value content Maximum water/solids ratio with swellin solids able bentonite mixture non-swelling swellable (weight %) bentonite bentonite 0 0.75 0.75 0.75 10 0.8 0.95 1.06 20 0.85 1.05 1.3 50 1.1 3.0 6.0 Products which have a very high bentonite content and a high water content are not, however, adequately solid. In products in which the solids are 50% bentonite, the limit water solids ratio is 2, which is a W/Z value of 4. A further limitation on the usefulness of setting water and solids mixtures is provided by the requirement that the density must not be below 1.3. By increasing the water - solids ratio of cement products by the addition of swellable bentonite thereto not only reduces the volume of the product, but also provides a weight reduction which is significant because of the reduction brought about thereby in transportation costs. The following table shows the relative increases of density, volume and weight in various water - solids contents compared with water. Cement and swellable bentonite is assumed to have a density of 3 for the purposes of this table.
Water/ Density Volume Weight Solids increase factor increase factor 0.33 2 2 4 0.5 1.8 1.67 3 0.8 1.59 1.42 2.25 1.0 1.5 1.33 2 1.2 1.43 1.28 1.83 1.5 1.36 1.22 1.67 1.9 1.30 1.18 1.53 oo 100% 1 1 1 (water)

Claims (3)

1. A method of disposal of tritium-containing water wastes in which the HTO-containing water wastes are mixed with an inorganic bonding agent, the mixture then being packaged and allowed to set in the packaging, the solidification product and the packaging then being suitable for sinking into the sea comprising the steps of mixing tritium-water or water containing synthetic radionuclides and tritium water with a bentonite which is capable of swelling and is water absorbent, the weight ratio of water to bentonite lying within the range of 10:1 to 4:1, adding cement of a cement and sand mixture to the bentonite-water mixture in a ratio by weight which is not less than 1 ::5 so as to produce a mortar which sets to a cement stone or concrete having a water-cement value of from 1.0 to 4.0, charging the liquid cement or mortar thus obtained into a plastics material or metal envelope and allowing the liquid cement or mortar to set in such envelope, the solidified product and packaging being suitable for sinking into the sea.
2. A method of disposal of tritium-containing water wastes in which the HTO-containing water wastes are mixed with an inorganic bonding agent, the mixture then being packaged and allowed to set in the packaging, the solidification product and the packaging then being suitable for sinking into the sea comprising the steps of mixing swellable, water absorbent bentonite with cement in a weight ratio lying in the range of 1: 9 to 1:1 and subsequently adding tritium water or water containing synthetic radionuclides and tritium water in an amount sufficient to produce a water-cement value of from 1.0 to 4.0, charging the liquid cement or mortar thus obtained into a plastics material or metal envelope and allowing the liquid cement or mortar to set in such envelope, the solidified product and packaging being suitable for sinking into the sea.
3. A method of disposal of tritium containing waste waters substantially as hereinbefore described.
GB8013241A 1979-04-27 1980-04-22 Method of disposal of tritium containing water wastes Expired GB2049261B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19792917060 DE2917060C2 (en) 1979-04-27 1979-04-27 Process for the solidification of tritiated water

Publications (2)

Publication Number Publication Date
GB2049261A true GB2049261A (en) 1980-12-17
GB2049261B GB2049261B (en) 1982-10-20

Family

ID=6069390

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8013241A Expired GB2049261B (en) 1979-04-27 1980-04-22 Method of disposal of tritium containing water wastes

Country Status (6)

Country Link
JP (1) JPS60638B2 (en)
BE (1) BE881627A (en)
CH (1) CH644965A5 (en)
DE (1) DE2917060C2 (en)
FR (1) FR2455341A1 (en)
GB (1) GB2049261B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2139583C1 (en) * 1998-06-08 1999-10-10 Белгородская государственная технологическая академия строительных материалов (БелГТАСМ), Курская АЭС Method for hardening radioactive wastes

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3539474A1 (en) * 1985-11-07 1987-05-21 Didier Werke Ag Process for filling a space in a salt dome
DE3543391A1 (en) * 1985-12-07 1987-06-11 Kernforschungsz Karlsruhe METHOD FOR STRENGTHENING TRITIUM FROM HTO CONTAINING LIQUIDS
DE3642975C1 (en) * 1986-12-17 1988-02-11 Wiederaufarbeitung Von Kernbre Process for the production of a solid product suitable for final storage of tritium-containing waste water
RU2154866C1 (en) * 1999-08-11 2000-08-20 Государственное унитарное предприятие "Научно-исследовательский, проектно-конструкторский и технологический институт бетона и железобетона" Method for disposal of reactor compartments of recovered submarines and nuclear-powered vessels
JP2015158424A (en) * 2014-02-24 2015-09-03 清水建設株式会社 Tritium water disposal method and facility

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL271326A (en) * 1958-12-31
DE2228938A1 (en) * 1972-06-14 1974-01-03 Nukem Gmbh Radio-active slurry disposal - by solidification and drum containment
DE2819086C2 (en) * 1978-04-29 1985-09-12 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the solidification of radioactive, aqueous waste liquids

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2139583C1 (en) * 1998-06-08 1999-10-10 Белгородская государственная технологическая академия строительных материалов (БелГТАСМ), Курская АЭС Method for hardening radioactive wastes

Also Published As

Publication number Publication date
FR2455341A1 (en) 1980-11-21
DE2917060A1 (en) 1980-10-30
JPS55147397A (en) 1980-11-17
GB2049261B (en) 1982-10-20
CH644965A5 (en) 1984-08-31
BE881627A (en) 1980-05-30
FR2455341B1 (en) 1984-03-23
DE2917060C2 (en) 1983-10-27
JPS60638B2 (en) 1985-01-09

Similar Documents

Publication Publication Date Title
US5304709A (en) Hazardous wast disposal method and composition
US3859799A (en) Landfill disposal of power plant wastes
US4581162A (en) Process for solidifying radioactive waste
US4952242A (en) Composition for solidification or semi-solidification of waste materials
CA2106747C (en) Preparation of inorganic hardenable slurry and method for solidifying wastes with the same
US4424148A (en) Process for preparing wastes for non-pollutant disposal
GB2049261A (en) Method of disposal of tritium- containing water wastes
ATE38217T1 (en) PROCEDURE FOR DISPOSAL OF SLUDGE.
EP0006329A1 (en) Encapsulating wastes
JPS5815000B2 (en) Radioactive waste disposal method
US5180542A (en) Container
RU2083006C1 (en) Radiation-shielding compound
CA1205097A (en) Process for preparing wastes for non-pollutant disposal
RU2139584C1 (en) Method of solidification of filter-perlite pulps
JPS62267699A (en) Method of solidifying and processing radioactive waste
JPH0727075B2 (en) Method for solidifying radioactive waste
JPS54142861A (en) Method of treating harmful sludge
JPS623698A (en) Solidifying processing method of radioactive waste
JPS6288999A (en) Method of solidifying and processing radioactive incombustible solid waste
JPS56152798A (en) Manufacture of granulated loam from sludge
Debus et al. Process for preparing wastes for non-pollutant disposal
JPS6191600A (en) Solidification method of radioactive concentrated waste liquid
JPH0677073B2 (en) Solidification material for radioactive waste treatment
Gablin et al. Radioactive waste disposal of water containing waste using urea-formaldehyde resin
JPS6483723A (en) Underwater banking work using self-hardening sand

Legal Events

Date Code Title Description
PCNP Patent ceased through non-payment of renewal fee