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
  • G21F9/10—Processing by flocculation
• • C—CHEMISTRY; METALLURGY
  • C01—INORGANIC CHEMISTRY
  • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
  • C01G43/00—Compounds of uranium

Definitions

• This sprouting relates to a method for treating a radioactive liquid waste in which uranium is removed at a high yield from a radiation waste liquid containing uranium in the presence of hydrogen peroxide.
• Dissolving the scrub in glass is a simple method of producing uranium, uranium and trio in scrap, and adding hydrogen peroxide.
• the method of removing the remaining uranium and / or stream eluted as a precipitate is described in Japanese Patent No. 551-11191 (Makikai Sho 56-1099825) No.) This is indicated in the description.
• the hydrogen peroxide contains 2 to J weight ⁇ and uranium contains 300- / 0. About 0 O mg / £ is contained.
• the present applicant has proposed a method for removing and recovering uranium from waste liquid containing uranium in a high yield. Water glass is added to water glass, which has a high production rate and a good transient water glass. ⁇ ⁇ Lan sedimentation 3 ⁇ 4Once obtained, it is easier to process the sedimentation of Uranium ⁇ And a method of turning it into a uranium nitrate solution (Japanese Patent Publication No. 8-3830 and Japanese Patent Publication No. 57-5319).
• a lath precipitation method When treating wastewater containing uranium in the coexistence of hydrogen peroxide by the water glass precipitation method, uranium with a concentration of ⁇ / OOng g remains, far exceeding the standard for wastewater discharge. Because of this, it was necessary to reduce the residual amount of perran in combination with other treatment methods. If the water glass precipitation method is applied after removing the co-existing hydrogen peroxide from the uranium-containing waste liquid in which ⁇ 2 to ⁇ J weight of hydrogen peroxide coexists, the residual amount of uranium is Q / ⁇ 3 ⁇ 4 ⁇ or less, and we saw that the emission standard ⁇ fell below a. In this way, even if hydrogen chloride coexists with uranium in the waste liquid, the removal rate of uranium is reduced by removing hydrogen oxide before the water glass sedimentation method. & Watched o
• the method of removing hydrogen peroxide in a solution is the decomposition of hydrogen peroxide by the wave method.
• this method is not industrially suitable because it requires not only] JU heat flux but also requires a long time for its decomposition.
• a method of decomposing hydrogen peroxide in a solution a method of adding a reagent that decomposes hydrogen peroxide may be considered, however, this method uses only hydrogen peroxide.
• Uranium coexists because it is decomposed and removed. ⁇ ⁇ ⁇ ⁇ In the assault intended, the reagent becomes a harmful substance S and the removal rate of uranium by the water glass precipitation method Worsen.
• the inventors of the present invention have found that, in the method of treating radioactive waste liquid containing uranium in the coexistence of hydrogen peroxide, hydrogen peroxide is separated out by water glass precipitation while separating hydrogen peroxide. ⁇ Seiichi who does not disturb the last IS As a result of repeated studies to find an additive, the present invention has been reached.
• This invention provides a method for treating radioactive wastewater that removes lanane at a higher rate than radioactive wastewater containing lanane in the presence of hydrogen peroxide.
• Radioactive waste liquid characterized by adding to the K-irradiated waste liquid a type selected from the group consisting of alky sulfite, hydrazine, manganese clay, ferric iron, and caustic alkali. Is a processing method.
• the present invention is more suitable for the waste liquid containing peranne in the presence of hydrogen peroxide than the group consisting of calcium sulfite, hydrazine, manganese salt, ferric salt, and sulfuric acid.
• the hydrogen index (pH) of the waste solution is adjusted to an alkaline solution, and the resulting precipitate is removed.
• an additive used in the present invention as described above, coexisting hydrogen peroxide is removed and a water glass precipitation method is used.
• the additives in the present invention are sulfites, hydrazines, manganese salts, secondary salts, and caustic alkaline.
• Alkaline sulphite is a sulphite soda or a sulphite liquor, which works together with hydrazine as a reducing agent for hydrogen hydride, such as manganese salts such as manganese, Ferric salts such as ferrous iron are chalky as a medium of ⁇ , and caustic is caustic soda and caustic, and is a t-additive of hydrogen peroxide.
• Each of these additives is effective at decomposing and removing coexisting hydrogen peroxide at the appropriate added amount, and uranium is removed by the water glass precipitation method.
• the additives do not appear as interfering substances on the surface. The amount of additives added is within the specified ranges as shown in the table below.
• the amount of sulfuric acid added depends on the physicochemical equivalent of alkali sulfite required to decompose hydrogen peroxide contained in the waste liquid.
• the amount of hydrazine added is inadequate, and the amount of hydrazine added is the theory of hydrazine necessary for the reduction of hydrogen peroxide contained in wastewater.
• the amount of manganese salt added should be at least ⁇ / times the weight of hydrogen peroxide contained in the waste liquid as the amount of manganese in terms of manganese.
• the amount of the ferric salt to be added may be ⁇ ⁇ 2 times or more of the weight of hydrogen peroxide contained in the waste liquid in terms of iron.
• the hydrogen ion “” on index ( ⁇ ⁇ ) of the waste liquid must be greater than or equal to 'f : desirably.
• the hydrogen ion index (PH) impurities contained in the waste liquid, such as aluminum, iron, and magnesium, are mainly contained in the lance club.
• Lead, etc. are converted to hydroxides by ammonia water or caustic alkaline, respectively, and are precipitated and removed.
• the stoichiometric equivalent of soda sulfite required for hydrogen peroxide separation as a reducing agent for hydrogen peroxide is added to wastewater / powder containing ⁇ 70% of hydrogen peroxide and uranium 070mg ⁇ . After adding the corresponding sulfurous acid / g and stirring for / min, the hydrogen ion index (pH) was adjusted to ⁇ with ammonia water, and the resulting precipitate was added. 3 g of water glass was added to the obtained liquid and stirred for / minute.
• Manganese nitrate was added as a manganese nitrate as a manganese-equivalent amount to ⁇ 2 g to the wastewater / hydrogen peroxide ⁇ 2% by weight, uranium-rich mgZ. Stirred for minutes. The hydrogen ion exponent (pH) was adjusted to te with ammonia water, and the sediment produced was separated by fr ⁇ . Then, water glass g was added to the obtained liquid, and the mixture was separated for one hour. After stirring, the formed water glass-uranium precipitate was separated. The obtained water-glass-uranium precipitate is treated with acetic acid to turn uranium, and uranium is turned as nitrate. By this treatment, the lanthanum content in the waste liquid klO- ⁇
• the resulting water glass-uranium precipitate is treated with nitrate to recover lanthanum, and uranium is recovered as an alternative salt.
• the uranium content in the waste liquid was ⁇ O mg.
• the table shows the results with the treatment method according to the present invention and for comparison with the treatment method according to the present invention for the lanthanum in the presence of hydrogen peroxide: Wastewater from water glass Before the treatment, the type of additive and the wastewater of the additive / the amount of the additive added were changed, and the amount of uranium in the wastewater when the wastewater treatment method using waterglass was performed Is shown.
• the wastewater treatment method of the present invention was CU0, whereas the wastewater had a water content of 0 mg / kg. It showed a permean content of ⁇ 04 tmg / g, confirming that the erection was remarkable.
• the present invention is a method for treating radioactive waste liquid in which uranium is removed from the uranium-containing radioactive waste liquid in the presence of hydrogen peroxide at a high rate. Additives for decomposing and removing the confined hydrogen contained in the radioactive waste liquid do not hinder the subsequent removal of uranium by the water glass precipitation method as an interfering substance. INDUSTRIAL APPLICABILITY
• the present invention can be used as a treatment method for removing oran from an orane-containing waste liquid at an extremely high rate.
• the method for treating a radioactive waste liquid generated by this method is inexpensive, easy, and easy.
• the emission standard of benzene Ct / rng i can be less than the helium content.

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• Chemical & Material Sciences (AREA)
• Organic Chemistry (AREA)
• Physics & Mathematics (AREA)
• Geology (AREA)
• Inorganic Chemistry (AREA)
• General Life Sciences & Earth Sciences (AREA)
• Life Sciences & Earth Sciences (AREA)
• Engineering & Computer Science (AREA)
• General Engineering & Computer Science (AREA)
• High Energy & Nuclear Physics (AREA)
• Removal Of Specific Substances (AREA)
• Inorganic Compounds Of Heavy Metals (AREA)
• Treatment Of Water By Oxidation Or Reduction (AREA)

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Citations (3)

• 1981
  • 1981-04-16 JP JP56057594A patent/JPS57172298A/ja active Granted
• 1982
  • 1982-04-16 WO PCT/JP1982/000123 patent/WO1982003722A1/ja active Application Filing
  • 1982-04-16 DE DE19823241293 patent/DE3241293C2/de not_active Expired

Patent Citations (3)

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