JPS63315998A - Treatment of radioactive waste liquid - Google Patents
Treatment of radioactive waste liquidInfo
- Publication number
- JPS63315998A JPS63315998A JP15237887A JP15237887A JPS63315998A JP S63315998 A JPS63315998 A JP S63315998A JP 15237887 A JP15237887 A JP 15237887A JP 15237887 A JP15237887 A JP 15237887A JP S63315998 A JPS63315998 A JP S63315998A
- Authority
- JP
- Japan
- Prior art keywords
- sodium
- waste liquid
- radioactive
- heating
- radioactive waste
- 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
Links
- 239000007788 liquid Substances 0.000 title claims abstract description 48
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 22
- 239000007787 solid Substances 0.000 claims abstract description 18
- 230000002285 radioactive effect Effects 0.000 claims abstract description 17
- 238000010438 heat treatment Methods 0.000 claims abstract description 16
- 238000001704 evaporation Methods 0.000 claims abstract 2
- 150000003388 sodium compounds Chemical class 0.000 claims description 15
- 238000003672 processing method Methods 0.000 claims 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract description 15
- 239000011734 sodium Substances 0.000 abstract description 15
- 229910052708 sodium Inorganic materials 0.000 abstract description 15
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 abstract description 12
- KKCBUQHMOMHUOY-UHFFFAOYSA-N sodium oxide Chemical compound [O-2].[Na+].[Na+] KKCBUQHMOMHUOY-UHFFFAOYSA-N 0.000 abstract description 8
- 229910001948 sodium oxide Inorganic materials 0.000 abstract description 8
- 235000010344 sodium nitrate Nutrition 0.000 abstract description 6
- 239000004317 sodium nitrate Substances 0.000 abstract description 6
- 238000003756 stirring Methods 0.000 abstract 1
- 239000002699 waste material Substances 0.000 description 16
- 238000000034 method Methods 0.000 description 15
- 239000002927 high level radioactive waste Substances 0.000 description 11
- 239000000463 material Substances 0.000 description 11
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 9
- 239000010426 asphalt Substances 0.000 description 6
- 239000007789 gas Substances 0.000 description 5
- 238000007496 glass forming Methods 0.000 description 5
- 239000002925 low-level radioactive waste Substances 0.000 description 5
- 238000000354 decomposition reaction Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- PFUVRDFDKPNGAV-UHFFFAOYSA-N sodium peroxide Chemical compound [Na+].[Na+].[O-][O-] PFUVRDFDKPNGAV-UHFFFAOYSA-N 0.000 description 4
- 239000000126 substance Substances 0.000 description 4
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 3
- 238000009835 boiling Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 239000011521 glass Substances 0.000 description 3
- 238000002156 mixing Methods 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 3
- 150000003839 salts Chemical class 0.000 description 3
- 229910052938 sodium sulfate Inorganic materials 0.000 description 3
- 235000011152 sodium sulphate Nutrition 0.000 description 3
- 238000007711 solidification Methods 0.000 description 3
- 230000008023 solidification Effects 0.000 description 3
- 230000008016 vaporization Effects 0.000 description 3
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N Iron oxide Chemical compound [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 238000012958 reprocessing Methods 0.000 description 2
- PUZPDOWCWNUUKD-UHFFFAOYSA-M sodium fluoride Chemical compound [F-].[Na+] PUZPDOWCWNUUKD-UHFFFAOYSA-M 0.000 description 2
- 239000002910 solid waste Substances 0.000 description 2
- 229910052717 sulfur Inorganic materials 0.000 description 2
- 239000011593 sulfur Substances 0.000 description 2
- 238000009834 vaporization Methods 0.000 description 2
- QAOWNCQODCNURD-UHFFFAOYSA-L Sulfate Chemical compound [O-]S([O-])(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-L 0.000 description 1
- NINIDFKCEFEMDL-UHFFFAOYSA-N Sulfur Chemical compound [S] NINIDFKCEFEMDL-UHFFFAOYSA-N 0.000 description 1
- 229910052768 actinide Inorganic materials 0.000 description 1
- 150000001255 actinides Chemical class 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- ZPUCINDJVBIVPJ-LJISPDSOSA-N cocaine Chemical compound O([C@H]1C[C@@H]2CC[C@@H](N2C)[C@H]1C(=O)OC)C(=O)C1=CC=CC=C1 ZPUCINDJVBIVPJ-LJISPDSOSA-N 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000012212 insulator 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
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000011775 sodium fluoride Substances 0.000 description 1
- 235000013024 sodium fluoride Nutrition 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- VGBPIHVLVSGJGR-UHFFFAOYSA-N thorium(4+);tetranitrate Chemical compound [Th+4].[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O VGBPIHVLVSGJGR-UHFFFAOYSA-N 0.000 description 1
- 238000004017 vitrification Methods 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
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
- G21F9/08—Processing by evaporation; by distillation
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は、再処理工場や原子力発電所等から発生する各
種放射性廃液を加熱処理し、それに含まれているナトリ
ウム化合物を分解・気化して除去することにより、最終
処分体の大幅な減容化を達成できるようにした放射性廃
液の処理方法に関するものである。[Detailed Description of the Invention] [Industrial Application Field] The present invention heat-treats various radioactive waste fluids generated from reprocessing plants, nuclear power plants, etc., and decomposes and vaporizes the sodium compounds contained therein. The present invention relates to a method for treating radioactive waste liquid that can significantly reduce the volume of a final disposal body by removing it.
［従来の技術］
原子炉や各種原子力関連施設等からは硝酸ナトリウム、
硫酸ナトリウム、水酸化ナトリウム等のナトリウム化合
物を含む放射性廃液が大量に発生する。[Conventional technology] Sodium nitrate,
A large amount of radioactive waste liquid containing sodium compounds such as sodium sulfate and sodium hydroxide will be generated.
例えば再処理工場からは高レベル廃液や中低レベル廃液
が生じる。高レベル廃液は主として大量の硝酸ナトリウ
ムと少量の核分裂生成物よりなり、一般に大量のガラス
形成材を添加し溶融固化することによってガラス固化体
にする処理方法が採用されている。また中低レベル廃液
は、主として硝酸ナトリウムと′ＲＸ量の核分裂生成物
よりなり、アスファルトやプラスチックと混合加熱して
アスファルト同化体やプラス千ツク同化体にすることに
より処理されている。For example, reprocessing plants produce high-level waste liquid and medium-low level waste liquid. The high-level waste liquid mainly consists of a large amount of sodium nitrate and a small amount of nuclear fission products, and generally a large amount of glass-forming material is added and melted and solidified to form a vitrified body. The medium and low level waste liquid mainly consists of sodium nitrate and nuclear fission products in an amount of 'RX', and is treated by mixing it with asphalt or plastic and heating it to form asphalt assimilates or plus-sulfur assimilates.
更に高速炉から発生する使用済燃料に付着したナトリウ
ムや腐食生成物を洗浄した放射性廃液には水酸化ナトリ
ウムが含まれている。この種の廃液は蒸発乾燥後、ガラ
ス形成材を添加し溶融固化してガラス同化体にしている
。Furthermore, the radioactive waste liquid that is used to wash away sodium and corrosion products from spent fuel generated from fast reactors contains sodium hydroxide. After this type of waste liquid is evaporated and dried, a glass forming material is added and melted and solidified to form a glass assimilate.
［発明が解決しようとする問題点］
良い性状（性質）のガラス固化体を作るには、ガラス中
に含ませることのできるナトリウム量に限界がある。高
レベル廃液を良好なガラス固化体にするためには大量の
ガラス形成材を投入しなけばならず廃棄物発生量が非常
に多くなる。[Problems to be Solved by the Invention] In order to produce a vitrified material with good properties, there is a limit to the amount of sodium that can be included in the glass. In order to convert high-level waste liquid into a good vitrified material, a large amount of glass-forming material must be added, resulting in a very large amount of waste.
また中低レベル廃液の処理に際して、硝酸ナトリウムや
硫酸ナトリウム等をアスファルトやプラス千ツク等と混
合加熱すると火災や爆発等の危険性があり、十分な注意
が必要で作業性が悪く好ましくない。In addition, when treating medium and low level waste liquids, mixing and heating sodium nitrate, sodium sulfate, etc. with asphalt, plastic sulfate, etc. poses a risk of fire or explosion, so sufficient caution is required and workability is poor and undesirable.
何れにしても廃液中に存在するナトリウム化合物のため
に大量の各種形成材が必要となり、最終処分体の容積が
著しく増大する大きな欠点があった。In any case, a large amount of various forming materials are required due to the sodium compounds present in the waste liquid, which has the major drawback of significantly increasing the volume of the final disposal body.
更に高レベル廃液をガラス固化してしまうと、廃液中に
含まれている有用元素の分離回収が困難になる問題もあ
る。Furthermore, if the high-level waste liquid is vitrified, there is also the problem that it becomes difficult to separate and recover useful elements contained in the waste liquid.
本発明の目的は、上記のような従来技術の欠点を解消し
、放射性廃液を加熱し続けるという確実で単純なプロセ
スにより廃液中のナトリウム化合物を分解・気化して除
去し、最終処分体の容積を著しく小さくし処理処分コス
トの大幅な削減を図ることができる放射性廃棄物の処理
ツノ法を提供することにある。The purpose of the present invention is to solve the above-mentioned drawbacks of the prior art, to decompose and vaporize sodium compounds in the waste liquid through a reliable and simple process of continuously heating the radioactive waste liquid, and to reduce the volume of the final disposal body. The object of the present invention is to provide a method for disposing of radioactive waste, which can significantly reduce the size of radioactive waste and significantly reduce treatment and disposal costs.
［問題点を解決するだめの手段］
上記のような目的を達成することのできる本発明は、ナ
トリウム化合物を含む放射性廃液を加熱蒸発させて乾燥
体にし、更に加熱を続けて含まれているナトリウム化合
物を分解・気化して分離除去し、放射性固体残渣を得る
ように構成した放射性廃液の処理方法である。[Means for Solving the Problems] The present invention, which can achieve the above objects, heats and evaporates radioactive waste liquid containing sodium compounds to dry it, and then continues to heat it to remove the sodium contained therein. This is a radioactive waste liquid treatment method configured to separate and remove compounds by decomposing and vaporizing them to obtain a radioactive solid residue.
本発明は高レベル廃液の処理のみならず、中低レベル廃
ｔ＆の処理など、各種ナトリウム化合物を含む廃液処理
に適用できる。The present invention is applicable not only to the treatment of high-level waste liquids, but also to the treatment of waste liquids containing various sodium compounds, such as the treatment of medium- and low-level waste liquids.
［作用］
放射性廃液は加熱によってその液体成分が蒸発し乾燥体
になる。そして更に加熱し続けることによって含まれて
いた各種ナトリウム化合物が分解・気化して分離除去さ
れ、放射性固体残渣が残留する。これによって処理すべ
き放射性廃棄物量を、大幅に減容できることになる。[Function] When the radioactive waste liquid is heated, its liquid component evaporates and becomes a dry substance. By continuing to heat it further, the various sodium compounds contained therein are decomposed and vaporized and separated and removed, leaving a radioactive solid residue. This will significantly reduce the amount of radioactive waste that must be treated.
例えば高レベル廃液の場合には、放射性固体残渣は核分
裂生成物、アクチニド、腐食生成物等よりなり、主とし
て酸化物の状態となっているから特にガラス固化しなく
てもよい。従って有用元素の回収も容易に行えるし、そ
のままで将来の有用元素回収のための一時貯蔵も可能と
なる。For example, in the case of high-level waste liquid, the radioactive solid residue consists of nuclear fission products, actinides, corrosion products, etc., and is mainly in an oxide state, so it does not need to be vitrified. Therefore, the useful elements can be easily recovered, and it is also possible to temporarily store them as they are for future useful element recovery.
また中低レベル廃液等の場合にアスファルト固化やプラ
スチック固化を行う場合も安全に作業することができる
。It is also possible to work safely when asphalt solidification or plastic solidification is performed in the case of medium to low level waste liquid.
［実施例］
第１図は本発明方法を実施するための最も単純な装置構
成を示す説明図である。共振型マイクロ波加熱器本体１
０の下部には放射性廃液１２を収容するルツボ１４がフ
ランジ１６によって取り付けられている。放射性廃液１
２は、ルツボ１４を取り付ける前に予め充填しておくか
、もしくは上部の注入管１８から連続的もしくはバッチ
的に供給される。[Example] FIG. 1 is an explanatory diagram showing the simplest apparatus configuration for implementing the method of the present invention. Resonant microwave heater body 1
A crucible 14 containing radioactive waste liquid 12 is attached to the lower part of 0 by a flange 16. Radioactive waste liquid 1
2 is filled in advance before installing the crucible 14, or is supplied continuously or batchwise from the upper injection pipe 18.
加熱に用いるマイクロ波はマイクロ波４波管取り付は目
２０から供給され、共振型マイクロ波加熱器で共振して
放射性廃液１２を集中加熱する。これによって液体成分
が蒸発して乾燥体となる。マイクロ波加熱を更に続行す
ると、廃液中に含まれていたナトリウム化合物は分解・
気化しｔＪ１気口２２を経てオフガス処理系に送られる
。このようにしてマイクロ波加熱により分解・気化しな
い放射性固体残渣２４がルツボ１４の底部に残留する。The microwave used for heating is supplied from the microwave 4-wave tube attachment point 20, resonates with a resonant microwave heater, and centrally heats the radioactive waste liquid 12. This causes the liquid component to evaporate and become a dry body. If microwave heating is continued further, the sodium compounds contained in the waste liquid will be decomposed and
It is vaporized and sent to the off-gas treatment system through the tJ1 air port 22. In this way, the radioactive solid residue 24 that is not decomposed or vaporized by microwave heating remains at the bottom of the crucible 14.
この放射性固体残渣２４は主として高沸点の成分よりな
る物質であり、ナトリウム化合物が除去されたため大幅
に減容される。This radioactive solid residue 24 is a substance mainly composed of components with high boiling points, and its volume is significantly reduced since the sodium compound is removed.
例えば高レベル廃液に含まれる固形分中の酸化ナトリウ
ム量は約４０％である。従って上記のようにナトリウム
分を除去すれば高レベル廃液に起因する放射性固体廃棄
物量は約６０％に減少する。更に従来、高レベル廃液を
ガラス固化する場合に高しベル廃液固形分約２５％（酸
化ナトリウムを含む）に対してガラス形成材約７５％の
割合でガラス溶融固化していた。ここでガラス形成材が
多い理由は、ナトリウムを安定なガラスに作るためであ
る。従って本発明のように高しベル廃液中からす１−リ
ウムを除去できると、放１１性固体残渣は王として酸化
物の形となり、ナトリウムを安定に固化するためにガラ
ス固化しなくてもよくなり、高しベル廃棄物同化体発生
用の大幅な減容（約１／７程度）が見込める。For example, the amount of sodium oxide in the solid content contained in high-level waste liquid is about 40%. Therefore, if the sodium content is removed as described above, the amount of radioactive solid waste resulting from high-level waste liquid will be reduced to about 60%. Furthermore, conventionally, when high-level waste liquid is vitrified, the solid content of the high-level waste liquid is about 25% (including sodium oxide) and the glass forming material is about 75%. The reason why there are so many glass forming materials here is to make sodium into a stable glass. Therefore, if sodium 1-lium can be removed from high-grade waste liquid as in the present invention, the radioactive solid residue will mainly be in the form of oxide, and vitrification will not be necessary to stably solidify sodium. Therefore, a significant volume reduction (approximately 1/7) can be expected for the generation of high-quality waste assimilate.
このように本発明方法で得られた放射性固体残渣は、こ
のままか若しくは発生ずるりへの除去処理等の安定化処
理を行ってから処分することもできるし、また１７来、
有用元素を回収するための一次貯蔵にも適している。As described above, the radioactive solid residue obtained by the method of the present invention can be disposed of as is or after stabilization treatment such as removal treatment of the generated residue.
It is also suitable for primary storage for recovering useful elements.
実際に高放射性模凝廃液を使って加熱実験した結果によ
れば、固形分７６．５４ｇ／７！を含む模１疑廃液Ｉρ
をマイクロ波２ｋＷで１時間加熱したところ、約２１ｇ
の加熱残留物を得ることができた。このことはナトリウ
ム化合物と低沸点の模凝放射性各種が除去されたことを
示しており、本発明方法が有効なことが判る。According to the results of an actual heating experiment using highly radioactive simulated condensate, the solid content was 76.54g/7! Sample 1 waste liquid Iρ containing
When heated in a 2kW microwave for 1 hour, approximately 21g
It was possible to obtain a heating residue of . This shows that sodium compounds and various low-boiling-point imitative radioactive substances were removed, and it can be seen that the method of the present invention is effective.
なお加熱により気化するような低沸点の放射性１亥種（
例えばセシウｌ、等）１まオフガス処理系で回収され別
途処■１１！されるごとになる。In addition, low-boiling point radioactive species (1) that vaporize when heated
For example, Cecil, etc.) 1 is recovered in the off-gas treatment system and treated separately ■ 11! It becomes every time it is done.
第２図は本発明方法を実施するのに好適な他の処理装置
を示す説明図である。ｆｌｌ’を酸ナトリウムを含む放
射性廃液３０は貯槽３２に蓄えられ、スクリューフィー
ダ弐マイクロ波脱硝装置３４に住人管３６を経て供給さ
れる。供給された放射性廃液３０は、マイクロ波導波管
３８から入ってくるマイクロ波により加熱され脱硝体と
なる。即ら加熱することにより硝酸ナトリウムは３８０
℃で分解して酸素を放出して亜１ｉｌｌｉ酸ナトリウム
になり、更に加熱を綺けると７５０°Ｃ以上で過酸化ナ
トリウムに、次いで酸化ナトリウムになる。被加熱対象
物はスクリュー１１０により攪拌混合されながら移送さ
れる。分解生成した排ガスはＩＦ気口４２から排出され
オフガス処理系へ送られる。FIG. 2 is an explanatory diagram showing another processing apparatus suitable for carrying out the method of the present invention. A radioactive waste liquid 30 containing sodium fluoride is stored in a storage tank 32 and is supplied to a screw feeder and a microwave denitrification device 34 via a drain pipe 36. The supplied radioactive waste liquid 30 is heated by microwaves coming from the microwave waveguide 38 and becomes denitrified. That is, by heating, sodium nitrate becomes 380
It decomposes at 750°C and releases oxygen to form sodium illlite, and when heated further, it becomes sodium peroxide and then sodium oxide at temperatures above 750°C. The object to be heated is transferred while being stirred and mixed by the screw 110. The decomposed exhaust gas is discharged from the IF port 42 and sent to the off-gas treatment system.
過酸化ナトリうムや酸化すｌ・リウムを含む被加熱対象
物は脱硝体抜き出し口４４から抜き出され、酸化ナトリ
ウム分解装置４６に送られる。The object to be heated containing sodium peroxide and sulfur/lium oxide is extracted from the denitrification outlet 44 and sent to the sodium oxide decomposition device 46.
この酸化ナトリウム分解装置４６は共振型マイクロ波加
熱器からなり、フランジ５２によってルツボ５０がその
下部に取り付けられた構造である。分解に用いるマイク
ロ波エネルギーはマイクロ波導波管取り付は口５４から
供給され、酸化ナトリウムや過酸化ナトリウムおよびナ
トリウムを含む被加熱対象物を加熱する。例えば酸化ナ
トリウムは４００℃以上で過酸化ナトリウムとナトリウ
ムに分解され、ナトリウムは沸点８７７．５℃、気化熱
１１００ｃａｌ／ｇで気化する。放射性固体残渣５８は
ルツボ５０内に残留する。気化した物質は排気口６０を
経て排出され、外部のオフガス処理系で処理される。This sodium oxide decomposition device 46 is composed of a resonant microwave heater, and has a structure in which a crucible 50 is attached to the lower part thereof by a flange 52. Microwave energy used for decomposition is supplied from the microwave waveguide attachment port 54 to heat objects to be heated, including sodium oxide, sodium peroxide, and sodium. For example, sodium oxide is decomposed into sodium peroxide and sodium at temperatures above 400°C, and sodium vaporizes with a boiling point of 877.5°C and a heat of vaporization of 1100 cal/g. Radioactive solid residue 58 remains within crucible 50. The vaporized substances are discharged through the exhaust port 60 and treated with an external off-gas treatment system.
以上本発明の好ましい実施例について詳述したが、本発
明はこのような構成のみに限定されるものでないことは
無論である。加りヘ方法については特に制限はない。し
かし本実施例のようにマイクロ波を利用して加熱すると
、ナトリウム化合物が内部から加熱されるためルツボの
内面にナトリウム化合物の層ができ、それが保温機能を
果たし、分解・気化を容易に実施できるし、またルツボ
の耐熱性の問題も特に生しない等の利点がある。Although preferred embodiments of the present invention have been described in detail above, it goes without saying that the present invention is not limited to only such a configuration. There are no particular restrictions on the addition method. However, when heating using microwaves as in this example, the sodium compound is heated from within, forming a layer of sodium compound on the inner surface of the crucible, which functions as a heat insulator and facilitates decomposition and vaporization. It has the advantage that it does not cause problems with the heat resistance of the crucible.
中低レベル廃液に含まれる同化体は放射性物質よりも塩
が多く含まれている。このため従来技術では塩の含有量
の４〜５倍のアスファルトで混合し固化体を作っていた
。ところが本発明のようなプロセスで塩を除去すること
ができるから、アスファル］・固化体の発生量も大幅に
減少する。The assimilates contained in medium- and low-level wastewater contain more salt than radioactive substances. For this reason, in the prior art, asphalt was mixed with 4 to 5 times the salt content to form a solidified product. However, since the salt can be removed by the process of the present invention, the amount of asphalt solidified material generated is also significantly reduced.
なお、本発明は硝酸すトリウムを含む廃液処理の他、硫
酸ナトリウムや水酸化ナトリウム二γを含む廃液処理に
も十分適用可能である。Note that the present invention is fully applicable to the treatment of waste liquids containing sodium sulfate and sodium hydroxide in addition to the treatment of waste liquids containing thorium nitrate.
また廃液中に含まれている放射性物質をなるべく放射性
固体として残留させるためには、水酸化鉄や酸化鉄のよ
うに放射性核種と結合吸着する物質を加えて処理するこ
とも有効である。In addition, in order to ensure that the radioactive substances contained in the waste liquid remain as radioactive solids as much as possible, it is also effective to add a substance that binds and adsorbs radionuclides, such as iron hydroxide or iron oxide, to the waste liquid.
［発明の効果］
本発明は上記のように加執によりナトリウム化合物を分
解除去して放射性固体残渣を得る処理方法であるから、
加熱という確実で華純なプロセスのみで固体廃棄物発生
量の大幅な減容を実現できる優れた効果がある。[Effects of the Invention] The present invention is a treatment method for obtaining a radioactive solid residue by decomposing and removing sodium compounds through compression as described above.
It has the excellent effect of significantly reducing the amount of solid waste generated using only the reliable and simple process of heating.
例えば本発明方法で高レベル廃液を処理した場合には、
ナトリウムを除去した残渣は主として酸化物となり特に
ガラス固化しなくてもよく、そのため更に廃棄物発生量
が少なくなるし、前記残渣から含有されている有用元素
を回収することも容易に行える。For example, when high-level waste liquid is treated using the method of the present invention,
The residue from which sodium is removed is mainly an oxide and does not need to be vitrified, which further reduces the amount of waste generated and makes it easy to recover the useful elements contained in the residue.
また各種形成材を加えて固化処理する場合でも、本発明
によってナトリウム分が除去されたために形成材の混合
吋を少なくでき、全体として大幅な最終廃棄物の減容化
を達成できる。Furthermore, even in the case of solidification treatment with the addition of various forming materials, since the sodium content is removed by the present invention, the amount of mixing of forming materials can be reduced, making it possible to achieve a significant volume reduction of the final waste as a whole.
第１図は本発明方法を実施するだめの加熱処理装置の一
例を示す説明図、第２図は本発明方決を実施するための
他の処理装置を示す説明図である。
１０・・・共振型マイクロ波加熱器本体、１２・・・放
射性廃液、１４・・・ルツボ、１６・・・フランジ、Ｉ
８・・・注入管、２０・・・マイクロ波４波管取り付は
口、２２・・・排気口、２４・・・放射性固体残渣。FIG. 1 is an explanatory diagram showing an example of a heat treatment apparatus for implementing the method of the present invention, and FIG. 2 is an explanatory diagram showing another treatment apparatus for implementing the method of the present invention. DESCRIPTION OF SYMBOLS 10... Resonance type microwave heater main body, 12... Radioactive waste liquid, 14... Crucible, 16... Flange, I
8... Injection pipe, 20... Microwave 4-wave tube attachment port, 22... Exhaust port, 24... Radioactive solid residue.
Claims (1)
て乾燥体にし、更に加熱を続けて含まれているナトリウ
ム化合物を分解・気化して分離除去し、放射性固体残渣
を得ることを特徴とする放射性廃液の処理方法。1. A radioactive waste liquid that is characterized by heating and evaporating a radioactive waste liquid containing sodium compounds to dry it, and then continuing to heat it to decompose and vaporize the contained sodium compounds and separate and remove them to obtain a radioactive solid residue. processing method.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15237887A JPH0648316B2 (en) | 1987-06-18 | 1987-06-18 | Treatment method of radioactive waste liquid |
| DE19883820092 DE3820092A1 (en) | 1987-06-18 | 1988-06-13 | Process for treating liquid radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15237887A JPH0648316B2 (en) | 1987-06-18 | 1987-06-18 | Treatment method of radioactive waste liquid |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63315998A true JPS63315998A (en) | 1988-12-23 |
| JPH0648316B2 JPH0648316B2 (en) | 1994-06-22 |
Family
ID=15539217
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15237887A Expired - Fee Related JPH0648316B2 (en) | 1987-06-18 | 1987-06-18 | Treatment method of radioactive waste liquid |
Country Status (2)
| Country | Link |
|---|---|
| JP (1) | JPH0648316B2 (en) |
| DE (1) | DE3820092A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH680198A5 (en) * | 1990-07-06 | 1992-07-15 | Sulzer Ag |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0766076B2 (en) * | 1990-08-14 | 1995-07-19 | 動力炉・核燃料開発事業団 | Continuous heating denitration equipment by microwave |
| JPH10337401A (en) * | 1997-03-12 | 1998-12-22 | Nukem Nuklear Gmbh | Method and device for concentrating salt-containing solution |
| ES2184540B2 (en) * | 1999-10-26 | 2004-09-16 | Equipos Nucleares, S.A. | PROCEDURE FOR TREATMENT OF RADIOACTIVE LIQUID WASTE AND ITS LATER STORAGE. |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2704147C2 (en) * | 1977-02-02 | 1986-04-10 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Process for the production of a stable solidification product containing radioactive substances which can be finally stored |
| AT349402B (en) * | 1977-05-24 | 1979-04-10 | Oesterr Studien Atomenergie | METHOD FOR PRODUCING SOLID PARTICLES |
| DE2818803C3 (en) * | 1978-04-28 | 1980-11-27 | Metallgesellschaft Ag, 6000 Frankfurt | Sludge incineration in a fluidized bed furnace |
| JPS5698696A (en) * | 1980-01-10 | 1981-08-08 | Hitachi Ltd | Method of processing radioactive liquid waste |
| DE3131276C2 (en) * | 1981-08-07 | 1986-02-13 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Process for the solidification of radioactive waste |
| JPS58191998A (en) * | 1982-05-06 | 1983-11-09 | 動力炉・核燃料開発事業団 | Cyclic tank type microwave heating device |
| DE3238962C2 (en) * | 1982-10-21 | 1985-01-17 | Nukem Gmbh, 6450 Hanau | Process for the solidification of aqueous radioactive waste solutions containing alkali nitrate |
-
1987
- 1987-06-18 JP JP15237887A patent/JPH0648316B2/en not_active Expired - Fee Related
-
1988
- 1988-06-13 DE DE19883820092 patent/DE3820092A1/en not_active Ceased
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH680198A5 (en) * | 1990-07-06 | 1992-07-15 | Sulzer Ag |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0648316B2 (en) | 1994-06-22 |
| DE3820092A1 (en) | 1989-01-12 |
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