JPH01235899A - Treatment for solidifying nitrate-containing radioactive waste liquid - Google Patents
Treatment for solidifying nitrate-containing radioactive waste liquidInfo
- Publication number
- JPH01235899A JPH01235899A JP6232288A JP6232288A JPH01235899A JP H01235899 A JPH01235899 A JP H01235899A JP 6232288 A JP6232288 A JP 6232288A JP 6232288 A JP6232288 A JP 6232288A JP H01235899 A JPH01235899 A JP H01235899A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- radioactive waste
- solidifying
- nitrate
- silicon dioxide
- 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.)
- Pending
Links
- 239000007788 liquid Substances 0.000 title claims abstract description 69
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 64
- 229910002651 NO3 Inorganic materials 0.000 title claims description 13
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 title claims description 13
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims abstract description 41
- 235000012239 silicon dioxide Nutrition 0.000 claims abstract description 20
- 239000000463 material Substances 0.000 claims abstract description 19
- 239000000377 silicon dioxide Substances 0.000 claims abstract description 19
- 238000007711 solidification Methods 0.000 claims abstract description 10
- 230000008023 solidification Effects 0.000 claims abstract description 10
- 238000001704 evaporation Methods 0.000 claims abstract description 7
- 230000008020 evaporation Effects 0.000 claims abstract description 6
- 239000002699 waste material Substances 0.000 claims abstract description 6
- 238000000034 method Methods 0.000 claims description 34
- 239000000126 substance Substances 0.000 claims description 27
- 230000008018 melting Effects 0.000 claims description 8
- 238000002844 melting Methods 0.000 claims description 8
- 239000002002 slurry Substances 0.000 claims description 8
- 150000002823 nitrates Chemical class 0.000 claims description 7
- 229910052783 alkali metal Inorganic materials 0.000 claims description 6
- 150000001340 alkali metals Chemical class 0.000 claims description 6
- 229910052784 alkaline earth metal Inorganic materials 0.000 claims description 6
- 150000001342 alkaline earth metals Chemical class 0.000 claims description 6
- 239000002925 low-level radioactive waste Substances 0.000 claims 2
- 238000002156 mixing Methods 0.000 abstract description 7
- 239000011521 glass Substances 0.000 abstract description 6
- 230000002285 radioactive effect Effects 0.000 abstract description 6
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 abstract description 5
- 230000001678 irradiating effect Effects 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 238000007796 conventional method Methods 0.000 description 6
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 description 4
- 238000001354 calcination Methods 0.000 description 4
- 238000001035 drying Methods 0.000 description 4
- 239000002585 base Substances 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 239000010453 quartz Substances 0.000 description 2
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 2
- 238000003756 stirring Methods 0.000 description 2
- 206010073306 Exposure to radiation Diseases 0.000 description 1
- 229910021529 ammonia Inorganic materials 0.000 description 1
- 238000003421 catalytic decomposition reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 235000014413 iron hydroxide Nutrition 0.000 description 1
- NCNCGGDMXMBVIA-UHFFFAOYSA-L iron(ii) hydroxide Chemical compound [OH-].[OH-].[Fe+2] NCNCGGDMXMBVIA-UHFFFAOYSA-L 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 239000003595 mist Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000006060 molten glass Substances 0.000 description 1
- 239000012768 molten material Substances 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 235000010344 sodium nitrate Nutrition 0.000 description 1
- 239000004317 sodium nitrate Substances 0.000 description 1
- 159000000000 sodium salts Chemical class 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野〕
本発明は、放射性廃液の固化処理方法に係わり、特に、
硝酸塩を含有する放射性廃液の固化処理方法に関する。[Detailed Description of the Invention] (Industrial Application Field) The present invention relates to a method for solidifying radioactive waste liquid, and in particular,
This invention relates to a method for solidifying radioactive waste liquid containing nitrates.
近時、例えば、特開昭５５−１２１８９７号公報に開示
されるように、マイクロ波を用いて放射性廃液を処理す
ることが行なわれている。Recently, radioactive waste liquid has been treated using microwaves, as disclosed in, for example, Japanese Unexamined Patent Publication No. 55-121897.
従来、硝酸塩を含有する放射性廃液の処理は、乾燥工程
により放射性廃液を乾燥した後、か焼工程により硝酸塩
を分解し、これを固化工程により固化することにより行
なわれている。Conventionally, treatment of radioactive waste liquid containing nitrate has been carried out by drying the radioactive waste liquid in a drying process, decomposing the nitrate in a calcination process, and solidifying it in a solidification process.
しかしながら、従来の方法では、乾燥工程、か焼工程お
よび固化工程がそれぞれ別の装置により行なわれている
ため、各工程間において放射性の廃液残渣を移動する必
要があり、工程が複雑であるという問題があった。However, in the conventional method, the drying process, calcination process, and solidification process are performed using separate equipment, so radioactive waste liquid residue must be moved between each process, making the process complicated. was there.
また、従来、高レベル放射性廃液のガラス固化方法とし
て、溶融ガラスに放射性廃液を直接供給して固化する方
法があるが、この従来の方法では、ベースの固化物質が
すでにガラス材料であるため、＼
大量の不純物を混入するとガラス組成を得ることができ
なくなるため放射性廃液を少量しか加える事ができず、
生成固化物中におけるベースの固化物質の割合が大きく
、放射性廃液の減容比が非常に小さいという問題があっ
た。In addition, conventional methods for vitrifying high-level radioactive waste liquid include directly supplying the radioactive waste liquid to molten glass and solidifying it, but in this conventional method, the base solidifying substance is already a glass material, If a large amount of impurities are mixed in, it will not be possible to obtain a glass composition, so only a small amount of radioactive waste liquid can be added.
There was a problem in that the proportion of the base solidified substance in the solidified product was large, and the volume reduction ratio of the radioactive waste liquid was very small.
本発明は、かかる従来の問題を解決するためになされた
もので、同一装置内において放射性廃液の固化を可能に
することができるとともに、放射性廃液の減容比を従来
より大幅に増大することのできる硝酸塩含有放射性廃液
の固化処理方法を提供することを目的とする。The present invention was made in order to solve such conventional problems, and it is possible to solidify radioactive waste liquid within the same device, and to greatly increase the volume reduction ratio of radioactive waste liquid compared to the conventional method. The purpose of the present invention is to provide a method for solidifying nitrate-containing radioactive waste liquid.
本発明にかかわる硝酸塩含有放射性廃液の固化処理方法
は、アルカリ金属あるいはアルカリ土類金属等の硝酸塩
を含有する放射性廃液を固化する硝酸塩含有放射性廃液
の固化処理方法において、レトルト内に収容される少量
の固化物質をマイクロ波の照射により溶融状態とした後
、この溶融状態の固化物質の上面に、二酸化珪素あるい
は二酸化珪素含有物の混合されたスラリー状の放射性廃
液を直接供給し、水分を蒸発した後、蒸発残渣を前記固
化物質とともに再度溶融し、この廃液供給。The method for solidifying radioactive waste liquid containing nitrates according to the present invention is a method for solidifying radioactive waste liquids containing nitrates that solidifies radioactive waste liquids containing nitrates such as alkali metals or alkaline earth metals. After the solidified substance is molten by microwave irradiation, a radioactive waste liquid in the form of a slurry containing silicon dioxide or a substance containing silicon dioxide is directly supplied onto the top of the molten solidified substance, and after the moisture is evaporated, , remelting the evaporation residue together with the solidified substance and supplying this waste liquid.
残渣溶融を繰り返す事により固化処理を行なうものであ
る。The solidification process is performed by repeatedly melting the residue.
本発明においては、レトルト内に収容される固化物質が
マイクロ波の照射により溶融状態とされた後、この溶融
状態の固化物質の上面に、二酸化珪素あるいは二酸化珪
素含有物の混合されたスラリー状の放射性廃液が直接供
給され、水分が蒸発され、この後、蒸発残渣が前記固化
物質とともに再度溶融され、この溶融物の上面にさらに
スラリー状放射性廃液が直接供給され、この工程を繰り
返す事により固化処理が行なわれる。In the present invention, after the solidified material contained in the retort is molten by microwave irradiation, a slurry containing silicon dioxide or a silicon dioxide-containing substance is applied onto the top surface of the molten solidified material. The radioactive waste liquid is directly supplied, water is evaporated, the evaporation residue is melted again together with the solidified substance, and the slurry radioactive waste liquid is further directly supplied onto the top of this melt, and this process is repeated to solidify. will be carried out.
以下、本発明方法の詳細を図面を用いて説明する。 Hereinafter, details of the method of the present invention will be explained using the drawings.
図は、本発明方法で使用される硝酸塩含有放射性廃液の
固化処理装置を示すもので、図において符号１１は、レ
トルト１３を下部に有し、マイクロ波を熱源とするイン
キャンメトル型の溶融炉を示している。The figure shows a solidification treatment apparatus for nitrate-containing radioactive waste liquid used in the method of the present invention. In the figure, reference numeral 11 is an in-can-metre type melting furnace that has a retort 13 at the bottom and uses microwaves as a heat source. It shows.
この溶融炉１１には、制御装置１５により制御される、
例えば、２４５０ＭＨｚ・５Ｋｗのマイクロ波発生装置
１７の導波管１９が、炉内放射能を封止するための石英
板１６を介して接続されている。また、マイクロ波の整
合を取るためのＥＨチューナ１８が、放射能汚染をさけ
るために、石英板１６の上流（発生器側）に配置されて
いる。This melting furnace 11 is controlled by a control device 15.
For example, a waveguide 19 of a 2450 MHz/5 Kw microwave generator 17 is connected via a quartz plate 16 for sealing radioactivity in the furnace. Further, an EH tuner 18 for matching microwaves is arranged upstream of the quartz plate 16 (on the generator side) to avoid radioactive contamination.
図において符号２１は、撹拌翼２３を有する混合槽を示
しており、この混合槽２１には、放射性廃液供給管２５
および二酸化珪素供給管２７が開口している。In the figure, reference numeral 21 indicates a mixing tank having a stirring blade 23, and this mixing tank 21 includes a radioactive waste liquid supply pipe 25.
And the silicon dioxide supply pipe 27 is open.
混合槽２１には、放射性廃液導入管２９の一端が開口し
ており、この放射性廃液導入管２９の他端は、溶融炉１
１の上部に開口している。放射性廃液導入管２９には、
制御装置１５により開閉される開閉弁３１およびポンプ
３３が配置されている。また、廃ガス中には、廃液の乾
燥時に特に多量のＮＯｘが発生するため、アンモニア添
加による触媒分解式のＮＯｘ除去装置３４が配置されて
いる。このＮＯｘ除去装置３４には、アンモニアガスボ
ンベ３６からのアンモニアガスが供給され、この供給は
、ＮＯｘモニタ３８により制御される。One end of a radioactive waste liquid introduction pipe 29 is open to the mixing tank 21, and the other end of this radioactive waste liquid introduction pipe 29 is connected to the melting furnace 1.
It opens at the top of 1. In the radioactive waste liquid introduction pipe 29,
An on-off valve 31 and a pump 33 that are opened and closed by the control device 15 are arranged. Furthermore, since a particularly large amount of NOx is generated in the waste gas when the waste liquid is dried, a NOx removal device 34 of a catalytic decomposition type using ammonia addition is disposed. This NOx removal device 34 is supplied with ammonia gas from an ammonia gas cylinder 36, and this supply is controlled by a NOx monitor 38.
本発明方法は、以上のように構成された硝酸塩含有放射
性廃液の固化処理装置を用いて以下述べるようにして行
なわれる。The method of the present invention is carried out as described below using the apparatus for solidifying nitrate-containing radioactive waste liquid constructed as described above.
すなわち、本発明方法では、運転開始時には、先ず、予
め、レトルト１３内に収容される、例えば、ガラスから
なる少量の固化物質３５がマイクロ波発生装置１７によ
るマイクロ波の照射により溶融状態とされる。That is, in the method of the present invention, at the start of operation, first, a small amount of solidified substance 35 made of, for example, glass, which is housed in the retort 13, is brought into a molten state by irradiation with microwaves by the microwave generator 17. .
この後、制御装置１５によりマイクロ波の照射を停止あ
るいは制限した状態で、開閉弁３１が開とされ、所定量
のスラリー状の放射性廃液が放射性廃液導入管２９から
、溶融状態の固化物質の上面に直接供給される。After that, while the microwave irradiation is stopped or restricted by the control device 15, the on-off valve 31 is opened, and a predetermined amount of slurry-like radioactive waste is poured from the radioactive waste inlet pipe 29 onto the top surface of the molten solidified material. supplied directly to
なお、スラリー状の放射性廃液には、二酸化珪素あるい
は二酸化珪素含有物（例えば、珪砂）が、放射性廃液中
のアルカリ金属あるいはアルカリ土類金属の１化学当量
に対して１化学当量以上の割合で混合されている。この
混合は、混合槽２１において撹拌翼２３を回転すること
により行なわれる。In addition, silicon dioxide or a substance containing silicon dioxide (for example, silica sand) is mixed in the radioactive waste liquid in the form of a slurry at a ratio of 1 chemical equivalent or more per 1 chemical equivalent of the alkali metal or alkaline earth metal in the radioactive waste liquid. has been done. This mixing is performed by rotating the stirring blades 23 in the mixing tank 21.
また、この実施例では、放射性廃液には、硝酸ナトリウ
ム３５０ ｇ／ｌ！、水酸化鉄２００ｇ／ｆ二酸化珪素
３００ ｇ／ｌを含む模擬放射性廃液が使用されている
。In addition, in this example, the radioactive waste liquid contained 350 g/l of sodium nitrate! A simulated radioactive waste liquid containing 200 g/f iron hydroxide and 300 g/l silicon dioxide is used.
このスラリ、−状の模擬放射性廃液のレトルト１３内へ
の供給により水分が蒸発される。この放射性廃液の供給
後に、制御装置１５によりマイクロ波の照射が開始され
、固化物質３５が溶融され、この固化物質３５の上部に
乾燥状態で存在していた放射性残渣が溶融され、さらに
固化物質３５も溶融されて混合される。Water is evaporated by supplying this slurry or --shaped simulated radioactive waste liquid into the retort 13. After the radioactive waste liquid is supplied, microwave irradiation is started by the control device 15, the solidified substance 35 is melted, the radioactive residue present in a dry state on the top of this solidified substance 35 is melted, and the solidified substance 35 is further melted. are also melted and mixed.
以上のような処理を、レトルト１３内が、乾燥した放射
性残渣により充填されるまで繰り返すことにより、安定
なガラス固化体を得ることができる。なお、運転開始時
、すなわち、第１回目の放射性廃液の供給時には、溶融
状態の固化物質としてガラスからなる固化物質３５が使
用されるが、２回目以降の放射性廃液の供給時には、ス
ラリー状の放射性廃液に含有された二酸化珪素とアルカ
リ金属あるいはアルカリ土類金属の結合により形成され
たガラス状の固化物質３７が使用される。By repeating the above-described process until the inside of the retort 13 is filled with the dried radioactive residue, a stable vitrified material can be obtained. Note that at the start of operation, that is, at the time of the first supply of radioactive waste liquid, the solidified substance 35 made of glass is used as the solidified substance in a molten state, but when the radioactive waste liquid is supplied from the second time onward, radioactive liquid in the form of a slurry is used. A glass-like solidified substance 37 formed by a combination of silicon dioxide contained in the waste liquid and an alkali metal or an alkaline earth metal is used.
しかして、本発明方法では、レトルト１３内に収容され
る固化物質をマイクロ波の照射により溶融状態とした後
、この溶融状態の固化物質の上面に、二酸化珪素あるい
は二酸化珪素含有物の混合されたスラリー状の放射性廃
液を直接供給し、水分を蒸発した後、固化物質を再度溶
融し、この溶融状態の固化物質内に前記水分の蒸発した
放射性廃液の残渣を溶融混合し、固化処理を行なうよう
にしたので、放射性廃液の乾燥工程、か焼工程および固
化工程を同一の溶融炉１１内で行うことが可能となる。Therefore, in the method of the present invention, after the solidified material contained in the retort 13 is brought into a molten state by microwave irradiation, silicon dioxide or a silicon dioxide-containing material is mixed on the upper surface of the molten solidified material. The slurry-like radioactive waste liquid is directly supplied, the water is evaporated, the solidified substance is melted again, and the residue of the radioactive waste liquid from which the water has evaporated is melted and mixed into the molten solidified substance to perform the solidification process. Therefore, it becomes possible to perform the drying process, the calcination process, and the solidification process of the radioactive waste liquid in the same melting furnace 11.
この結果、放射性の廃液残渣を移動する必要がなくなり
、環境汚染および被曝を被る虞を解消することができる
。As a result, there is no need to move the radioactive waste liquid residue, and the risk of environmental contamination and exposure to radiation can be eliminated.
また、本発明方法では、放射性廃液中の主要成分である
硝酸塩をか焼して得られたアルカリ金属あるいはアルカ
リ土類金属がガラスマトリックスの一部とされるため、
生成固化物中における放射性残渣の割合が非常に大きく
なり、放射性廃液の減容比を従来より大幅に増大するこ
とができる。In addition, in the method of the present invention, alkali metals or alkaline earth metals obtained by calcining nitrates, which are the main components in radioactive waste liquid, are used as part of the glass matrix.
The ratio of radioactive residue in the produced solidified product becomes extremely large, and the volume reduction ratio of radioactive waste liquid can be significantly increased compared to the conventional method.
また、本発明方法では、放射性廃液を少量ずつ処理する
ことが可能となるため、装置の運転、停止を容易に行な
うことが可能となる。Furthermore, in the method of the present invention, it is possible to treat radioactive waste liquid little by little, so it is possible to easily operate and stop the apparatus.
さらに、以上述べた実施例では、マイクロ波の照射を停
止あるいは制限した状態で、溶融状態の固化物質の上面
に、放射性廃液を直接供給するようにしたので、水分の
蒸発に必要な熱エネルギを、溶融状態の固化物質３５か
ら有効に得ることができる。そして、この時には、マイ
クロ波の照射が停止あるいは制限されているため、水分
の蒸発に伴いミスト化したナトリウム塩等が、マイクロ
波エネルギにより電離されることはない。従って、レト
ルト１３内に導電性雰囲気が形成され、アークが発生す
るのを有効に防止することができる。Furthermore, in the embodiments described above, the radioactive waste liquid was directly supplied onto the top surface of the solidified material in the molten state while microwave irradiation was stopped or restricted, so that the thermal energy required for evaporating water was reduced. , can be effectively obtained from the solidified substance 35 in the molten state. At this time, since the microwave irradiation is stopped or limited, the sodium salts and the like that have become mist due to the evaporation of water are not ionized by the microwave energy. Therefore, a conductive atmosphere is formed within the retort 13, and arcing can be effectively prevented from occurring.
また、本発明では、密閉空間内において放射性廃液の処
理を行なうことが可能となるため、例えば、α核種を含
むＴＲＵ放射性廃液の処理に特に有効である。Furthermore, the present invention allows radioactive waste liquid to be treated in a closed space, and is therefore particularly effective in treating, for example, TRU radioactive waste liquid containing alpha nuclides.
〔発明の効果］
以上述べたように、本発明の硝酸塩含有放射性廃液の固
化処理方法によれば、レトルト内に収容される少量の固
化物質をマイクロ波の照射により溶融状態とした後、こ
の溶融状態の固化物質の上面に、二酸化珪素あるいは二
酸化珪素含有物の混合されたスラリー状の放射性廃液を
直接供給し、水分を蒸発した後、蒸発残渣を前記固化物
質とともに再度溶融し、この廃液供給、残渣溶融を繰り
返すことにより、固化処理を行なうようにしたので、同
一装置内において放射性廃液の固化を可能にすることが
できるとともに、放射性廃液の減容比を従来より大幅に
増大することができるという利点がある。[Effects of the Invention] As described above, according to the method for solidifying nitrate-containing radioactive waste liquid of the present invention, after a small amount of solidified material contained in a retort is brought into a molten state by irradiation with microwaves, this molten material is A radioactive waste liquid in the form of a slurry containing silicon dioxide or a substance containing silicon dioxide is directly supplied onto the upper surface of the solidified substance in the state, and after the water is evaporated, the evaporation residue is melted again together with the solidified substance, and this waste liquid is supplied. Since the solidification process is performed by repeatedly melting the residue, it is possible to solidify the radioactive waste liquid in the same device, and the volume reduction ratio of the radioactive waste liquid can be significantly increased compared to conventional methods. There are advantages.
図は本発明方法で使用される硝酸塩含有放射性廃液の固
化処理装置を示す説明図である。
〔主要な部分の符号の説明〕
１１・・・溶融炉
１３・ ・ ・レトルト
１７・・・マイクロ波発生装置
２１・・・混合槽。The figure is an explanatory diagram showing a solidification treatment apparatus for nitrate-containing radioactive waste liquid used in the method of the present invention. [Explanation of symbols of main parts] 11... Melting furnace 13... Retort 17... Microwave generator 21... Mixing tank.
Claims (4)
塩を含有する放射性廃液を固化する硝酸塩含有放射性廃
液の固化処理方法において、レトルト内に収容される少
量の固化物質をマイクロ波の照射により溶融状態とした
後、この溶融状態の固化物質の上面に、二酸化珪素ある
いは二酸化珪素含有物の混合されたスラリー状の放射性
廃液を直接供給し、水分を蒸発した後、蒸発残渣を前記
固化物質とともに再度溶融し、この廃液供給、残渣溶融
を繰り返す事により、固化処理を行なうことを特徴とす
る硝酸塩含有放射性廃液の固化処理方法。(1) In a method for solidifying radioactive waste containing nitrates, such as solidifying radioactive waste containing nitrates of alkali metals or alkaline earth metals, a small amount of solidified material contained in a retort is molten by microwave irradiation. After that, a radioactive waste liquid in the form of a slurry containing silicon dioxide or a substance containing silicon dioxide is directly supplied onto the top surface of this molten solidified material, and after the moisture is evaporated, the evaporation residue is melted again together with the solidified material. A method for solidifying a radioactive waste liquid containing nitrate, characterized in that the solidification process is carried out by repeating this process of supplying the waste liquid and melting the residue.
有する中低レベル放射性廃液である請求項１記載の硝酸
塩含有放射性廃液の固化処理方法。(2) The method for solidifying a nitrate-containing radioactive waste liquid according to claim 1, wherein the radioactive waste liquid is a medium-low level radioactive waste liquid containing 100 to 500 g/l of nitrate.
廃液（１００μＣｉ／ｃｃ以下）である請求項１または
２記載の硝酸塩含有放射性廃液の固化処理方法。(3) The method for solidifying a nitrate-containing radioactive waste liquid according to claim 1 or 2, wherein the radioactive waste liquid is a medium-low level waste liquid (100 μCi/cc or less) containing transuranium nuclides.
射性廃液中のアルカリ金属あるいはアルカリ土類金属の
１化学当量に対して１化学当量以上の割合で混合されて
いる請求項１ないし３のいずれか１記載の硝酸塩含有放
射性廃液の固化処理方法。(4) The slurry-like radioactive waste liquid contains silicon dioxide in a ratio of 1 chemical equivalent or more to 1 chemical equivalent of the alkali metal or alkaline earth metal in the radioactive waste liquid. The method for solidifying a nitrate-containing radioactive waste liquid according to any one of the above.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6232288A JPH01235899A (en) | 1988-03-16 | 1988-03-16 | Treatment for solidifying nitrate-containing radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6232288A JPH01235899A (en) | 1988-03-16 | 1988-03-16 | Treatment for solidifying nitrate-containing radioactive waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01235899A true JPH01235899A (en) | 1989-09-20 |
Family
ID=13196789
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6232288A Pending JPH01235899A (en) | 1988-03-16 | 1988-03-16 | Treatment for solidifying nitrate-containing radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01235899A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2659783A1 (en) * | 1990-03-14 | 1991-09-20 | Atomic Energy Authority Uk | METHOD AND APPARATUS FOR REMOVING TRITIUM FROM AN OBJECT. |
| JPH05161824A (en) * | 1991-12-16 | 1993-06-29 | Power Reactor & Nuclear Fuel Dev Corp | Treatment of waste alcohol solution with high salt concentration |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58132699A (en) * | 1982-02-03 | 1983-08-08 | 動力炉・核燃料開発事業団 | Method of melting and solidifying radioactive waste |
| JPS633299A (en) * | 1986-06-23 | 1988-01-08 | 三機工業株式会社 | Microwave melting solidifying method of liquid waste |
-
1988
- 1988-03-16 JP JP6232288A patent/JPH01235899A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58132699A (en) * | 1982-02-03 | 1983-08-08 | 動力炉・核燃料開発事業団 | Method of melting and solidifying radioactive waste |
| JPS633299A (en) * | 1986-06-23 | 1988-01-08 | 三機工業株式会社 | Microwave melting solidifying method of liquid waste |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2659783A1 (en) * | 1990-03-14 | 1991-09-20 | Atomic Energy Authority Uk | METHOD AND APPARATUS FOR REMOVING TRITIUM FROM AN OBJECT. |
| JPH05161824A (en) * | 1991-12-16 | 1993-06-29 | Power Reactor & Nuclear Fuel Dev Corp | Treatment of waste alcohol solution with high salt concentration |
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