WO2018132041A1 - Способ обращения с радиоактивными растворами - Google Patents
Способ обращения с радиоактивными растворами Download PDFInfo
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- WO2018132041A1 WO2018132041A1 PCT/RU2018/000010 RU2018000010W WO2018132041A1 WO 2018132041 A1 WO2018132041 A1 WO 2018132041A1 RU 2018000010 W RU2018000010 W RU 2018000010W WO 2018132041 A1 WO2018132041 A1 WO 2018132041A1
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- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
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- G21F9/16—Processing by fixation in stable solid media
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- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
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- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
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Definitions
- the invention relates to the field of environmental protection, and more specifically to the field of processing of radioactive waste and can be used for the safe and effective management of a large amount of liquid radioactive waste of various levels of activity resulting from the decontamination of protective equipment of boxes and chambers and allows to reduce the amount of stored waste by curing them and incorporating them into a ceramic matrix.
- radioactive waste containing radionuclides U, Th, Am, Cm, Pu, Np, as well as radioactive rare earth elements, Zr, Mo, Ru, Cs, Pd, Sr , Ba, Rb, is subjected to thermal concentration, the concentrate is mixed with oxides in the following ratio of components, mass.
- % concentrate of radioactive waste (in terms of oxides) - 15-30; T 2 - 50-60; CaO - 5-10; Zr0 2 - 5-20; A1 2 0 3 - 3-5; BaO - 3-10, after which the resulting mixture is mixed with carbon-containing material, taken in an amount of 3 - 10 wt.% Of the total mass of the charge, and the moisture content of the obtained carbon-containing mixture is adjusted to 5-20 wt.%.
- SUBSTITUTE SHEET (RULE 26) long-term storage, and the entire process of incorporating radioactive waste into ceramics is carried out at a pressure below atmospheric.
- Thermal concentration is carried out by incomplete dehydration (evaporation or drying) of radioactive waste, in which water is always present, and the use of not completely dehydrated radioactive waste instead of calcine prevents dust formation at the stage of preparation of the charge, which increases the safety of the method.
- Thermally concentrated radioactive waste is not only included in the resulting Synroc ceramics, but is also one of the starting components for the synthesis of perovskite, zirconolite and hollandite included in its composition.
- the closest analogue that coincides with the claimed invention for the largest number of essential features is a method for immobilizing highly active waste into a ceramic matrix (RF Patent JSfe 2315381 of 05.22.2006 “Method
- the specified method involves the calcination (denitration) of highly active waste and their mixing with oxides (in the following ratios: high active waste calcine from 10 to 20 wt.%; T 2 from 50 to 60 wt.%; CaO from 7.5 to 12.5 mass Wt.%; MnO from 7.5 to 12.5 wt.%; Fe 2 0 3 from 2.5 to 7.5 wt.%; A1 20 0 from 2.5 to 7.5 wt.%), Heating obtained mixtures at a pressure not lower than atmospheric to a maximum working temperature of 2000 ° C, holding at a working temperature and cooling to the formation of a monolithic material.
- the specified method is intended to include high-level waste with a high content of actinides and rare earth elements and is aimed at immobilizing and long-term geological storage of the actinide-rare-earth fraction of radioactive waste generated during the processing of spent nuclear fuel.
- the proposed method does not describe the possibility of incorporating high salt waste containing a significant amount of alkali metal cations, including those containing components of the compositions of acidic and alkaline solutions used to deactivate protective equipment.
- the process is energy intensive.
- the objective of this technical solution is to create a reliable simple way to immobilize non-technological waste to obtain a monolithic material suitable for long-term geological storage.
- SUBSTITUTE SHEET titanium, calcium, iron (III) and aluminum in a certain ratio, heat treatment and joint melting of all components to obtain a ceramic matrix and characterized in that zirconium and manganese oxides are additionally added to the mixture of calcinate with oxides of titanium, calcium, iron (III) and aluminum at the next
- Calcination of the solid residue from evaporation of decontamination solutions is carried out at a temperature of from 750 to 800 ° C for a complete 105 decomposition of nitrates and carbonates.
- Fusion of calcine with the mixture is carried out at a temperature not lower than 1350 ° C for 1 hour to obtain a monolithic fused ceramic.
- zirconium dioxide and manganese in the mixture lowers the melting temperature of the ceramics, which makes the process less energy-consuming.
- the content of manganese oxide in the charge varies depending on the actual content of potassium permanganate in technological solutions after deactivation in terms of manganese.
- the phase composition of the ceramic may change.
- the solutions after deactivation can be evaporated to salts, and after their heat treatment to oxides, they can be mixed with the components of the mixture for the manufacture of ceramics, which in turn can be
- the product after evaporation and heat treatment at 350 ° ⁇ does not become perfectly dry and does not require additional introduction of moisture-enriched products to prevent dust formation, which reduces the emission of aerosols at the stage of mixing with the charge and simplifies the technological modes of melting the target ceramics.
- the content of manganese oxide can be adjusted depending on the actual content of potassium permanganate in technological solutions after deactivation in terms of manganese. In case of uneven mixing of acid and alkaline
- SUBSTITUTE SHEET (RULE 26) solutions as well as increasing or decreasing the proportion of potassium permanganate 150 in technological radioactive solutions, the composition shown in table 1 can be adjusted by decreasing or increasing the content in the initial mixture Mn0 2 .
- the entire composition is pre-treated at 800 ° C for 155 decomposition of nitrates and carbonates, and the resulting composition melts at 1350 ° C for 1 hour.
- the values of the leaching rate of the main components (cations) of the matrix are in the range of 10 " -10 " g / cm-day when the material is leached in hot bidistilled water at 90 ° C (sampling on days 3, 7 and 14).
Abstract
Description
Claims
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2019538194A JP6636680B1 (ja) | 2017-01-16 | 2018-01-16 | 放射性溶液取り扱いの方法 |
KR1020197020642A KR102067563B1 (ko) | 2017-01-16 | 2018-01-16 | 방사성 용액의 취급 방법 |
EP18738961.4A EP3570293B1 (en) | 2017-01-16 | 2018-01-16 | Method of handling radioactive solutions |
US16/478,291 US10614926B2 (en) | 2017-01-16 | 2018-01-16 | Method of handling radioactive solutions |
CN201880007102.2A CN110447077B (zh) | 2017-01-16 | 2018-01-16 | 处理放射性溶液的方法 |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
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RU2017101380 | 2017-01-16 | ||
RU2017101380A RU2643362C1 (ru) | 2017-01-16 | 2017-01-16 | Способ обращения с радиоактивными растворами после дезактивации поверхностей защитного оборудования |
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Publication Number | Publication Date |
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WO2018132041A1 true WO2018132041A1 (ru) | 2018-07-19 |
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PCT/RU2018/000010 WO2018132041A1 (ru) | 2017-01-16 | 2018-01-16 | Способ обращения с радиоактивными растворами |
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Country | Link |
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US (1) | US10614926B2 (ru) |
EP (1) | EP3570293B1 (ru) |
JP (1) | JP6636680B1 (ru) |
KR (1) | KR102067563B1 (ru) |
CN (1) | CN110447077B (ru) |
RU (1) | RU2643362C1 (ru) |
WO (1) | WO2018132041A1 (ru) |
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CN111004032A (zh) * | 2019-11-29 | 2020-04-14 | 广东工业大学 | 一种钙钛锆石型陶瓷固化体及其制备方法和应用 |
CN111138190A (zh) * | 2020-01-10 | 2020-05-12 | 广东工业大学 | 一种钙钛锆石型陶瓷固化体及其制备方法和应用 |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
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RU2131627C1 (ru) * | 1997-06-10 | 1999-06-10 | Производственное объединение "МАЯК" | Способ переработки сточных вод, содержащих перманганаты щелочных металлов |
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RU2153717C1 (ru) | 1998-12-23 | 2000-07-27 | Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (МосНПО "Радон") | Способ включения радиоактивных отходов в керамическую матрицу |
RU2315381C1 (ru) | 2006-05-22 | 2008-01-20 | Государственное унитарное предприятие города Москвы - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (ГУП МосНПО "Радон") | Способ иммобилизации высокоактивных отходов в керамическую матрицу |
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CN110447077A (zh) | 2019-11-12 |
EP3570293A4 (en) | 2020-10-28 |
KR20190111925A (ko) | 2019-10-02 |
CN110447077B (zh) | 2023-05-05 |
KR102067563B1 (ko) | 2020-01-17 |
JP6636680B1 (ja) | 2020-01-29 |
JP2020505590A (ja) | 2020-02-20 |
EP3570293B1 (en) | 2022-04-13 |
US20190371483A1 (en) | 2019-12-05 |
RU2643362C1 (ru) | 2018-02-01 |
US10614926B2 (en) | 2020-04-07 |
EP3570293A1 (en) | 2019-11-20 |
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