JPS6370198A - Volume-reduction processing method and device for spent nuclear-fuel reprocessing waste liquor - Google Patents
Volume-reduction processing method and device for spent nuclear-fuel reprocessing waste liquorInfo
- Publication number
- JPS6370198A JPS6370198A JP21534386A JP21534386A JPS6370198A JP S6370198 A JPS6370198 A JP S6370198A JP 21534386 A JP21534386 A JP 21534386A JP 21534386 A JP21534386 A JP 21534386A JP S6370198 A JPS6370198 A JP S6370198A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- spent nuclear
- fuel reprocessing
- nuclear fuel
- volume
- 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
- 239000002699 waste material Substances 0.000 title claims description 38
- 238000012958 reprocessing Methods 0.000 title claims description 17
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims description 15
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 title claims 3
- 238000003672 processing method Methods 0.000 title claims 2
- 239000007788 liquid Substances 0.000 claims description 49
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims description 31
- 229910052740 iodine Inorganic materials 0.000 claims description 31
- 239000011630 iodine Substances 0.000 claims description 31
- 230000002285 radioactive effect Effects 0.000 claims description 28
- 238000000034 method Methods 0.000 claims description 17
- 239000007789 gas Substances 0.000 claims description 15
- 239000002925 low-level radioactive waste Substances 0.000 claims description 9
- 238000010298 pulverizing process Methods 0.000 claims description 7
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical group [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 claims description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 4
- 229910052760 oxygen Inorganic materials 0.000 claims description 4
- 239000001301 oxygen Substances 0.000 claims description 4
- 229910052709 silver Inorganic materials 0.000 claims description 4
- 239000004332 silver Substances 0.000 claims description 4
- 239000003463 adsorbent Substances 0.000 claims description 3
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims description 3
- 238000007664 blowing Methods 0.000 claims description 3
- 238000001035 drying Methods 0.000 claims description 3
- 239000000463 material Substances 0.000 claims description 3
- 239000002253 acid Substances 0.000 claims description 2
- 239000012071 phase Substances 0.000 claims 3
- 150000007513 acids Chemical class 0.000 claims 1
- 239000007791 liquid phase Substances 0.000 claims 1
- 238000001179 sorption measurement Methods 0.000 claims 1
- 239000008188 pellet Substances 0.000 description 10
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 9
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 8
- 239000010409 thin film Substances 0.000 description 7
- 239000000843 powder Substances 0.000 description 6
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 5
- 229910017604 nitric acid Inorganic materials 0.000 description 5
- 238000009423 ventilation Methods 0.000 description 5
- 230000002378 acidificating effect Effects 0.000 description 4
- 239000004317 sodium nitrate Substances 0.000 description 4
- 235000010344 sodium nitrate Nutrition 0.000 description 4
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 description 3
- 229910001882 dioxygen Inorganic materials 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 3
- 239000002901 radioactive waste Substances 0.000 description 3
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- 239000003513 alkali Substances 0.000 description 2
- 230000005587 bubbling Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 description 2
- 238000005453 pelletization Methods 0.000 description 2
- 238000004378 air conditioning Methods 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 229910002092 carbon dioxide Inorganic materials 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- ZCYVEMRRCGMTRW-NJFSPNSNSA-N iodine-129 atom Chemical compound [129I] ZCYVEMRRCGMTRW-NJFSPNSNSA-N 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 210000004379 membrane Anatomy 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 210000004303 peritoneum Anatomy 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000002904 solvent Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は使用済核燃料再処理工程から排出される中低レ
ベル放射性廃液の減容方法に係シ、特に廃液中の放射性
ヨウ素の安定固化に好適な方法および装置に関する。[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a method for reducing the volume of medium to low level radioactive waste liquid discharged from a spent nuclear fuel reprocessing process, and in particular to a method for stably solidifying radioactive iodine in the waste liquid. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS OF THE INVENTION
使用済核燃料再処理工程から排出される中低レベル放射
性廃液の減容方法として、例えば特開昭６０−１８３５
９６に示されるように、炭酸ガス雰囲気下で乾繰様で廃
液を加熱して乾燥粉体化し、廃液中に含まれる放射性ヨ
ウ素を粉体中に移行させ、さらにベレット化する方法が
知られている。As a method for reducing the volume of medium and low level radioactive waste liquid discharged from the spent nuclear fuel reprocessing process, for example, Japanese Patent Application Laid-Open No. 60-1835
As shown in No. 96, a method is known in which the waste liquid is heated in a dry cycle in a carbon dioxide atmosphere to dry and powder it, the radioactive iodine contained in the waste liquid is transferred to the powder, and then the waste liquid is pelletized. There is.
この方法ではペレット中に放射性ヨウ素が含まれること
になる。ペレットの貯ｖ！、過程において湿度、温度等
の貯蔵雰囲気条件が変動した場合、放射性ヨウ素がペレ
ットから雰囲気ガス中へ移行する可能性があシ、放射性
ヨウ素の中には長半減期（１０７年）のヨウ素１２９が
含まれているので、ペレット貯蔵施設の換気系に設けた
除去装置において、これを除去する必要がある。This method results in radioactive iodine being contained in the pellets. Saving pellets! If the storage atmosphere conditions such as humidity and temperature change during the process, there is a possibility that radioactive iodine will migrate from the pellets into the atmospheric gas.Iodine-129, which has a long half-life (107 years), Therefore, it must be removed using a removal device installed in the ventilation system of the pellet storage facility.
上記従来技術はペレット貯蔵施設の換気系における放射
性ヨウ素の除去装置の容量が大きくなるという問題があ
った。これは従来技術ではペレット貯蔵施設が大規模に
なると換気風量が大きくなるためである。The above conventional technology has a problem in that the capacity of the radioactive iodine removal device in the ventilation system of the pellet storage facility becomes large. This is because in the conventional technology, when the pellet storage facility becomes large-scale, the ventilation air volume becomes large.
本発明の目的は使用済核燃料再処理廃液の乾燥粉体化の
前段で放射性ヨウ素を除去し、以てペレ、ト貯蔵施設換
気系中の放射性ヨウ素除去装置を省略し又はその容量を
低減することにある。The purpose of the present invention is to remove radioactive iodine at the stage before drying and pulverizing spent nuclear fuel reprocessing waste liquid, thereby omitting a radioactive iodine removal device in the ventilation system of a pellet storage facility or reducing its capacity. It is in.
〔問題点を解決するための手段〕
上記目的は、使用済核燃料再処理工程から排出される中
低レベル放射性廃液の粉体化処理の前段で、廃液のＰｌ
（３〜５の範囲に調整すると共に廃液中に酸素ガスを吹
き込むことにより、廃液中から放射性ヨウ素を気相中に
移行させた後これをフィルタで吸着除去することによシ
達成される。ヨウ素を吸着したフィルタは後に無機固化
材で安定固化することによシ処分することができる。[Means for solving the problem] The above purpose is to reduce the PlO of the waste liquid before the pulverization treatment of medium and low level radioactive waste liquid discharged from the spent nuclear fuel reprocessing process.
(This is achieved by adjusting the range of 3 to 5 and blowing oxygen gas into the waste liquid to transfer radioactive iodine from the waste liquid into the gas phase, and then adsorbing and removing it with a filter.Iodine The filter that has adsorbed this can be disposed of after being stably solidified with an inorganic solidifying agent.
使用済核燃料再処理工程から排出される中低レベル放射
性廃液中に溶解している放射性ヨウ素はイオン状で存在
しているが、廃液のｐＨを酸性にして酸素を吹き込むと
下記に示す反応によシイオン状のヨウ素が酸化されて分
子状となる。Radioactive iodine dissolved in the medium-low level radioactive waste liquid discharged from the spent nuclear fuel reprocessing process exists in the form of ions, but when the pH of the waste liquid is made acidic and oxygen is blown into it, the reaction shown below occurs. The ionic form of iodine is oxidized and becomes molecular.
分子状のヨウ素は揮発性であるため、酸素ガスのバブリ
ング作用によシ気相へ移行する。放射性ヨウ素の気相へ
の放出速度は大きいので、バブリング風量をそれ程大き
くする必要はない。気相へ移行した放射性ヨウ素はフィ
ルタで吸着除去される。Since molecular iodine is volatile, it moves into the gas phase due to the bubbling action of oxygen gas. Since the release rate of radioactive iodine into the gas phase is high, there is no need to increase the bubbling air volume so much. Radioactive iodine that has migrated to the gas phase is adsorbed and removed by a filter.
放射性ヨウ素吸着済のフィルタは後に無機固化材で固化
される。The filter with radioactive iodine adsorbed is later solidified with an inorganic solidifying material.
以下図面を参照して本発明の一実施例について説明する
。An embodiment of the present invention will be described below with reference to the drawings.
使用済核燃料再処理工場においては下記のように硝酸ナ
トリウムを主成分とする中低レベル放射性廃液が発生す
る。すなわち、核燃料再処理の抽出工程で使用したＴＢ
Ｐなどの溶媒は放射線損傷を受け、性能が低下している
ので、水酸化ナトリウムなどのアルカリを用いて洗浄処
理を行ない再使用されるが、洗浄液の水酸化す） ＩＪ
ウムは硝酸とともに中レベル放射性廃液に含まれ、水酸
化ナトリウムと硝酸の反応によシ硝酸ナトリウムが生成
するので、中レベル放射性廃液の主成分は硝酸ナトリウ
ムとなるのである。この廃液中には放射性ヨウ素が含ま
れている。At spent nuclear fuel reprocessing plants, medium- and low-level radioactive waste liquid containing sodium nitrate as the main component is generated as shown below. In other words, TB used in the extraction process of nuclear fuel reprocessing
Solvents such as P have been damaged by radiation and their performance has deteriorated, so they are cleaned and reused using an alkali such as sodium hydroxide, but the cleaning solution is oxidized (IJ).
Um is included in medium-level radioactive waste liquid along with nitric acid, and sodium nitrate is produced by the reaction between sodium hydroxide and nitric acid, so sodium nitrate is the main component of medium-level radioactive waste liquid. This waste liquid contains radioactive iodine.
この硝酸ナトリウムを主成分とする中低レベル放射性廃
液を第１図に示した廃液タンク１に送る。This medium-low level radioactive waste liquid containing sodium nitrate as a main component is sent to the waste liquid tank 1 shown in FIG.
次に、タンク１内の廃液の−を弱酸性域に調整する。す
なわち、声測定器１２によシ廃液の…を測定し、この値
がアルカリ域の場合には酸添加タンク２から硝酸を、ま
た〆（が強酸性域の場合にはアルカリ添加タンク３よシ
水酸化ナトリウム液を供給することによって廃液のｐＨ
を３〜５に％％ｕする。Next, the - of the waste liquid in the tank 1 is adjusted to a weakly acidic range. That is,... of the waste liquid is measured using the voice measuring device 12, and if this value is in the alkaline range, nitric acid is added from the acid addition tank 2, and if the value is in the strongly acidic range, nitric acid is added from the alkali addition tank 3. pH of waste liquid by feeding sodium hydroxide solution
%u to 3-5%.
この−調整後、給気管４よシ酸素ガスを廃液タンク１に
抜き込む。この操作によりａ液中に溶解していた放射性
ヨウ素が気相中に放出される。After this adjustment, oxygen gas is drawn into the waste liquid tank 1 through the air supply pipe 4. By this operation, radioactive iodine dissolved in liquid a is released into the gas phase.
第２図に放射性ヨウ素の気相への放出率と廃液の声との
関係を実験的に測定した結果を示す。本図よシ、廃液の
ｐＨを５以下の酸性域に調整することＫよシ溶液中の放
射性ヨウ素が大部分気相中へ放出されることがわかる。Figure 2 shows the results of experimental measurements of the relationship between the rate of release of radioactive iodine into the gas phase and the volume of waste liquid. This figure shows that by adjusting the pH of the waste solution to an acidic range of 5 or less, most of the radioactive iodine in the solution is released into the gas phase.
この反応は次のように考えられる。This reaction can be thought of as follows.
すなわち、廃液中のＩ−イオンが酸化され分子状のヨウ
素となシ、これが揮発性の性質を有するため、気相へ放
出されることになる。That is, the I- ions in the waste liquid are oxidized to form molecular iodine, which has volatile properties and is therefore released into the gas phase.
気相へ放出された放射性ヨウ素はフィルター５によシ捕
捉除去される。とのフィルタ内には例えば銀アルミナの
ような吸着材が充填されておシ、放射性ヨウ素が銀と反
応することによシ除去される。The radioactive iodine released into the gas phase is captured and removed by the filter 5. The filter is filled with an adsorbent such as silver alumina, and radioactive iodine is removed by reacting with silver.
以上のようにして放射性ヨウ素が完全に除去された廃液
は遠心薄膜乾燥機６によシ粉体化処理される。第３図は
遠心薄膜乾燥機６の一部断面図とした全体図である。放
射性廃液は廃液供給口１４から遠心膜乾燥様に導入され
、ディストビ、−タ１５によって遠心薄膜乾燥機を構成
している蒸発器の容器の伝熱面１７に一様に配分される
。このディストリビュー夕１５は蒸発器の中央に設けら
れた回転軸１８と、これに取り付けられた可動式のブレ
ード１９と、回転軸１８の駆動モータ２１からなる。グ
レード１９は蒸発器の内壁に近接して回転軸１８に取シ
付けられておシ１回転にともなう遠心力によシ外側に広
がって該内壁に接するようになっている。伝熱面１７上
を重力によって乎直に落下する廃液は伝熱面１７上に腹
膜を形成し、容器壁外側の加熱ジャケット１６内を流れ
る熱媒からの熱によって加熱され、蒸発乾燥される。The waste liquid from which radioactive iodine has been completely removed in the manner described above is pulverized by the centrifugal thin film dryer 6. FIG. 3 is an overall view, partially in section, of the centrifugal thin film dryer 6. The radioactive waste liquid is introduced from the waste liquid supply port 14 in the manner of centrifugal membrane drying, and is uniformly distributed by the distributor 15 onto the heat transfer surface 17 of the evaporator container constituting the centrifugal thin film dryer. The distributor 15 consists of a rotating shaft 18 provided at the center of the evaporator, a movable blade 19 attached to the rotating shaft 18, and a drive motor 21 for the rotating shaft 18. Grade 19 is attached to the rotating shaft 18 in close proximity to the inner wall of the evaporator, and is spread outward by the centrifugal force generated by one rotation of the evaporator to come into contact with the inner wall. The waste liquid falling directly on the heat transfer surface 17 by gravity forms a peritoneum on the heat transfer surface 17, is heated by the heat from the heating medium flowing in the heating jacket 16 outside the container wall, and is evaporated to dryness.
加熱シャケ、ト１６内を流れる熱媒としては例えば高圧
の蒸気が用いられる。上記ブレード１９は、回転ととも
に容器壁の伝熱面１７上に付着したスケールを除去する
。廃液は乾燥した粉体になるまで濃縮され、生成した粉
体は遠心薄膜乾燥機６の下端の粉体取出口２０から取シ
出される。また、廃液の蒸発によシ発生した蒸気は、遠
心薄膜乾燥機６の上部にある蒸気出口１３から排出され
、第１図に示すξストセパレータ８と復水器９に導入さ
れる。復水器９で蒸気は水に戻されて再使用される。For example, high-pressure steam is used as the heat medium flowing in the heating tank 16. The blade 19 removes scale deposited on the heat transfer surface 17 of the container wall as it rotates. The waste liquid is concentrated until it becomes a dry powder, and the generated powder is taken out from the powder outlet 20 at the lower end of the centrifugal thin film dryer 6. Further, the steam generated by the evaporation of the waste liquid is discharged from the steam outlet 13 at the top of the centrifugal thin film dryer 6, and introduced into the ξst separator 8 and condenser 9 shown in FIG. The steam is returned to water in the condenser 9 and reused.
遠心薄膜乾燥機６から生成された硝酸す） ＩＪウムを
主成分とする粉体は造粒機７でベレットに固められた後
、グローブゲックス１０に収納されたドラム缶１１に充
填される。ドラム缶は再処理工場の貯蔵庫に保管される
。The powder containing nitric acid as a main component produced by the centrifugal thin film dryer 6 is solidified into pellets in a granulator 7, and then filled into a drum 11 housed in a GlobeGex 10. The drums are stored in storage at the reprocessing plant.
一方、放射性ヨウ素を捕捉したフィルタ５内の銀アルミ
ナ等の吸着材は、その後、例えばセメントガラス等の無
機固化材で安定固化される。On the other hand, the adsorbent such as silver alumina in the filter 5 that has captured radioactive iodine is then stably solidified with an inorganic solidifying material such as cement glass.
使用済核燃料再処理工程から排出される中低レベル放射
性廃液中に含まれる放射性ヨウ素の中には半減期が１０
年と長いｌ−１２９があるが、前述のように、本発明実
施例においては放射性ヨウ素は粉体化・ペレット化の前
段で気相中へ放出されるのでベレット中には含まれず、
ベレット貯蔵庫における換気空調設備にヨウ素除去フィ
ルターの容量低減または省略が可能となる。Radioactive iodine contained in medium- and low-level radioactive waste liquid discharged from the spent nuclear fuel reprocessing process has a half-life of 10
However, as mentioned above, in the examples of the present invention, radioactive iodine is released into the gas phase before pulverization and pelletization, so it is not contained in the pellets.
It becomes possible to reduce the capacity or omit the iodine removal filter in the ventilation air conditioning equipment in the pellet storage.
本発明によれば、使用済核燃料再処理廃液の粉体化・ペ
レット化の前段において廃液中の放射性ヨウ素を除去す
ることができるので、ペレット貯Ｍ、施設の換気系中の
ヨウ素除去用フィルタの容量低減または省略が可能にな
る。According to the present invention, it is possible to remove radioactive iodine from spent nuclear fuel reprocessing waste liquid before pulverizing and pelletizing it. Capacity can be reduced or omitted.
第１図は本発明の一実施例を示すフローチャート図、第
２図は放射性ヨウ素の気相への放出率と、１４の関係を
示す図、第３図は遠心薄膜乾燥機の断面を示す図である
。Figure 1 is a flowchart showing an embodiment of the present invention, Figure 2 is a diagram showing the relationship between the release rate of radioactive iodine into the gas phase and 14, and Figure 3 is a diagram showing a cross section of a centrifugal thin film dryer. It is.
Claims (1)
放射性廃液を粉体化して減容処理する方法において、粉
体化処理の前段で廃液のｐＨを３〜５に調整すると共に
廃液中に酸素を吹き込むことにより廃液中から放射性ヨ
ウ素を気相中に移行させ、気相中に移行した該放射性ヨ
ウ素をフィルタで除去することを特徴とする使用済核燃
料再処理廃液の減容処理方法。 ２、フィルタは銀アルミナ吸着剤である特許請求の範囲
第１項記載の使用済核燃料再処理廃液の減容処理方法。 ３、放射性ヨウ素を吸着したフィルタを無機固化材で固
化する特許請求の範囲第１項又は第２項記載の使用済核
燃料再処理廃液の減容処理方法。 ４、使用済核燃料再処理工程から排出される中低レベル
放射性廃液を受け入れる廃液タンク、該廃液タンクへｐ
Ｈ調整用に添加するための酸およびアルカリを夫々収納
したタンク、上記廃液タンク中の液相内に酸素を吹き込
む酸素供給管、上記廃液タンク中の気相に接続された放
射性ヨウ素吸着用フィルタ、上記廃液タンクからの廃液
を乾燥粉体化する装置よりなることを特徴とする使用済
核燃料再処理廃液の減容処理装置。[Scope of Claims] 1. A method for reducing the volume of medium-low level radioactive waste liquid discharged from a spent nuclear fuel reprocessing process by pulverizing it, in which the pH of the waste liquid is adjusted to 3 to 5 before the pulverization process. A spent nuclear fuel reprocessing waste liquid characterized by adjusting and blowing oxygen into the waste liquid to transfer radioactive iodine from the waste liquid to the gas phase, and removing the radioactive iodine transferred to the gas phase with a filter. Volume reduction processing method. 2. The method for reducing the volume of spent nuclear fuel reprocessing waste liquid according to claim 1, wherein the filter is a silver alumina adsorbent. 3. A method for reducing the volume of spent nuclear fuel reprocessing waste liquid according to claim 1 or 2, wherein the filter adsorbing radioactive iodine is solidified with an inorganic solidifying material. 4. A waste liquid tank that receives medium and low level radioactive waste liquid discharged from the spent nuclear fuel reprocessing process, and a pail to the waste liquid tank.
A tank containing acids and alkalis to be added for H adjustment, an oxygen supply pipe for blowing oxygen into the liquid phase in the waste liquid tank, a radioactive iodine adsorption filter connected to the gas phase in the waste liquid tank, A volume reduction treatment device for spent nuclear fuel reprocessing waste liquid, characterized by comprising a device for drying and pulverizing the waste liquid from the waste liquid tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP21534386A JPS6370198A (en) | 1986-09-12 | 1986-09-12 | Volume-reduction processing method and device for spent nuclear-fuel reprocessing waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP21534386A JPS6370198A (en) | 1986-09-12 | 1986-09-12 | Volume-reduction processing method and device for spent nuclear-fuel reprocessing waste liquor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6370198A true JPS6370198A (en) | 1988-03-30 |
Family
ID=16670731
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP21534386A Pending JPS6370198A (en) | 1986-09-12 | 1986-09-12 | Volume-reduction processing method and device for spent nuclear-fuel reprocessing waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6370198A (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6031094A (en) * | 1983-08-01 | 1985-02-16 | 株式会社日立製作所 | Treating facility for radioactive waste |
| JPS6147595A (en) * | 1984-08-15 | 1986-03-08 | 株式会社日立製作所 | Device for removing iodine |
-
1986
- 1986-09-12 JP JP21534386A patent/JPS6370198A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6031094A (en) * | 1983-08-01 | 1985-02-16 | 株式会社日立製作所 | Treating facility for radioactive waste |
| JPS6147595A (en) * | 1984-08-15 | 1986-03-08 | 株式会社日立製作所 | Device for removing iodine |
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