JPS63248491A - Treatment of waste water containing actinide element - Google Patents
Treatment of waste water containing actinide elementInfo
- Publication number
- JPS63248491A JPS63248491A JP8367487A JP8367487A JPS63248491A JP S63248491 A JPS63248491 A JP S63248491A JP 8367487 A JP8367487 A JP 8367487A JP 8367487 A JP8367487 A JP 8367487A JP S63248491 A JPS63248491 A JP S63248491A
- Authority
- JP
- Japan
- Prior art keywords
- tannin
- waste water
- adsorbent
- actinide element
- immobilization
- 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
- 229910052768 actinide Inorganic materials 0.000 title claims abstract description 34
- 150000001255 actinides Chemical class 0.000 title claims abstract description 34
- 239000002351 wastewater Substances 0.000 title description 16
- 239000003463 adsorbent Substances 0.000 claims abstract description 26
- 238000000034 method Methods 0.000 claims abstract description 25
- 239000002354 radioactive wastewater Substances 0.000 claims abstract description 20
- 229920001864 tannin Polymers 0.000 claims abstract description 19
- 239000001648 tannin Substances 0.000 claims abstract description 19
- 235000018553 tannin Nutrition 0.000 claims abstract description 19
- QAOWNCQODCNURD-UHFFFAOYSA-N Sulfuric acid Chemical compound OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 claims abstract description 8
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims abstract description 5
- 229910017604 nitric acid Inorganic materials 0.000 claims abstract description 5
- 229910052770 Uranium Inorganic materials 0.000 claims description 12
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical group [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 claims description 5
- 229910052776 Thorium Inorganic materials 0.000 claims description 5
- 229910052778 Plutonium Inorganic materials 0.000 claims description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 2
- 238000003672 processing method Methods 0.000 claims 1
- 235000011511 Diospyros Nutrition 0.000 abstract description 3
- 244000236655 Diospyros kaki Species 0.000 abstract description 3
- 238000012856 packing Methods 0.000 abstract 1
- 238000007796 conventional method Methods 0.000 description 8
- 238000001179 sorption measurement Methods 0.000 description 8
- 230000000694 effects Effects 0.000 description 5
- 239000002253 acid Substances 0.000 description 4
- 238000003795 desorption Methods 0.000 description 4
- 239000011347 resin Substances 0.000 description 4
- 229920005989 resin Polymers 0.000 description 4
- 230000007423 decrease Effects 0.000 description 3
- 229910052500 inorganic mineral Inorganic materials 0.000 description 3
- 239000011707 mineral Substances 0.000 description 3
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 2
- 239000013522 chelant Substances 0.000 description 2
- 239000003456 ion exchange resin Substances 0.000 description 2
- 229920003303 ion-exchange polymer Polymers 0.000 description 2
- 150000003839 salts Chemical class 0.000 description 2
- 238000002336 sorption--desorption measurement Methods 0.000 description 2
- 238000005406 washing Methods 0.000 description 2
- 238000004065 wastewater treatment Methods 0.000 description 2
- 150000007513 acids Chemical class 0.000 description 1
- 230000002301 combined effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- UZUODNWWWUQRIR-UHFFFAOYSA-L disodium;3-aminonaphthalene-1,5-disulfonate Chemical compound [Na+].[Na+].C1=CC=C(S([O-])(=O)=O)C2=CC(N)=CC(S([O-])(=O)=O)=C21 UZUODNWWWUQRIR-UHFFFAOYSA-L 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000010970 precious metal Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J20/00—Solid sorbent compositions or filter aid compositions; Sorbents for chromatography; Processes for preparing, regenerating or reactivating thereof
- B01J20/22—Solid sorbent compositions or filter aid compositions; Sorbents for chromatography; Processes for preparing, regenerating or reactivating thereof comprising organic material
- B01J20/24—Naturally occurring macromolecular compounds, e.g. humic acids or their derivatives
Landscapes
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Organic Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Water Treatment By Sorption (AREA)
Abstract
Description
【発明の詳細な説明】
（産業分野）
本発明はアクチニド元素含有の放射性廃水において該ア
クチニド元禦儂度の低減化を目的とする放射性廃水の処
理方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Industrial Field) The present invention relates to a method for treating radioactive wastewater containing actinide elements, the purpose of which is to reduce the degree of elasticity of the actinide elements.
（従来技術とその問題点）
原子力施設から排出される廃水のうち、ウラン等のアク
チニド元素を含む！Ａ６水については可能な限り、これ
らアクチニド元業績変の低減化が望まれている。(Prior art and its problems) Wastewater discharged from nuclear facilities contains actinide elements such as uranium! Regarding A6 water, it is desired to reduce these changes in actinide performance as much as possible.
アクチニド元素を含む放射性廃水の処理方法としては従
来イオン交換樹脂吸着法及びキレート樹脂吸着法等があ
り、こハらの方法によってそれぞｆＬ醇廃水中のアクチ
ニド元１濃度の低減化がはかられてきた。Conventional methods for treating radioactive wastewater containing actinide elements include ion exchange resin adsorption methods and chelate resin adsorption methods, and these methods have each been used to reduce the concentration of actinide elements in fL wastewater. It's here.
しかしながら、これらの従来方法では＃廃水中に比較的
多量の共存塩が存在し、また廃水のｐｉ（ｈｔ８以上の
アルカル側であるのが一般的である。However, in these conventional methods, a relatively large amount of coexisting salts exist in the wastewater, and the wastewater is generally on the alkal side with pi(ht8 or more).
１＃廃水からのこれらアクチニド元素の除去は困難であ
った。また、従来方法で一般生活環境に放出できるレベ
ルまで、アクチニド元素＠度を低減しようとする場合に
は、該廃水の処理速度を遅くし、たとえば、固定層吸着
カラムにおけるＳｖ値を３０ ｈ−１未泗にする必要が
あるなど、処理能力の点においても問題があった。Removal of these actinide elements from 1# wastewater was difficult. In addition, when trying to reduce the actinide element concentration to a level that can be released into the general living environment using conventional methods, the treatment rate of the wastewater is slowed down, for example, the Sv value in the fixed bed adsorption column is reduced to 30 h-1. There were also problems in terms of processing power, such as the need for uninterrupted processing.
さらに、従来方法では、一度樹脂に吸着されたアクチニ
ド元素を硝酸等の鉱≦で脱着させる場合には、ｌ規定以
上の比較的高い嬶度の酸を必要とし、吸脱着サイクルの
繰返し使用において、樹脂の劣化の問題や酸の使用量が
多くなるなどの問題が発生した。Furthermore, in the conventional method, when desorbing the actinide elements once adsorbed on the resin with minerals such as nitric acid, a relatively high degree of acid with a strength exceeding 1 standard is required, and in repeated use of adsorption/desorption cycles, Problems arose, such as resin deterioration and the amount of acid used.
（発明の目的）
本発明者らは上記の従来方法の問題点を解決し、アクチ
ニド元素含有の放射性廃水の処Ｂ！能力を効率よくかつ
経済的に向上せしめ得る処理方法を提供すべく、種々研
究を重ねた結果、吸着体として固定化タンニン系吸着体
を使用することによって、上記の目的を達成し得ること
を見出し、本発明に到達した。(Objective of the Invention) The present inventors have solved the problems of the above-mentioned conventional method, and achieved a treatment method for radioactive wastewater containing actinide elements. In order to provide a treatment method that can improve the capacity efficiently and economically, we have conducted various studies and found that the above objectives can be achieved by using an immobilized tannin adsorbent as the adsorbent. , arrived at the present invention.
（゛発明の構成）
すなわち、本発明によれば、アクチニド元素含有の放射
性廃水の処理方法において、固定化タンニン系吸着体を
固定層カラムに充填し、該吸着体の単位量に対する１時
間当りの該放射性廃水通水量を５Ｖ＝３０〜３００ｈ
とすることを特徴とする放射性廃水の処理方法、が得ら
れる。(Structure of the Invention) That is, according to the present invention, in a method for treating radioactive wastewater containing actinide elements, a fixed bed column is filled with an immobilized tannin-based adsorbent, and the amount per hour per unit amount of the adsorbent is The radioactive wastewater flow rate is 5V = 30 to 300h.
A method for treating radioactive wastewater is obtained.
本発明で吸着体として使用される固定化タンニン系吸着
体は安価な固定化柿渋タンニン、固定化五倍子タンニン
などがあり、これら吸着体にアクチニド元素が吸着され
る機構の要因としては吸着体の分子構造、アクチニド元
素のイオン半径などが重要と考えられる。これらの要因
の綜合効果として、アクチニド元素、殊にウラン、トリ
ウム。The immobilized tannin-based adsorbents used as adsorbents in the present invention include inexpensive immobilized persimmon tannin and immobilized five-fold tannin, and the mechanism by which actinide elements are adsorbed to these adsorbents is The structure, ionic radius of the actinide element, etc. are considered to be important. The combined effect of these factors is that the actinide elements, especially uranium and thorium.
プルトニウムは吸着挙動を共にするものと判断される。It is judged that plutonium has the same adsorption behavior.
本発明方法では、従来のイオン交換樹脂吸着法やキレー
ト樹脂吸着法の場合の約ｌＯ倍程度のＳｖ値においても
、廃水中のアクチニド元素を充分に吸着除去することが
可能である。本発明方法において、Ｓｖ値が３００ ｈ
−’を越えると、第１図に示すように、アクチニド元素
の除去率が低下しはじめ、またＳｖ値が３０ｈ 未満
では充分に除去はできるものの、廃水処理効率が低下す
るので、不適当である。すなわち、本発明方法では工業
的にはＳｖ値は３０〜３００ｈ の範囲が必要であり、
好ましくは５０〜２００ｈ の範囲である。また、本
発明方法では、固定化タン二ノ系吸着体の再生は、０．
０１〜０．５規定の薄い鉱酸（希硝酸、希りＣ酸）で容
易に吸着アクチニド元素を脱着することができる。第２
図に示すように、該吸着体の１０回の繰９し使用におい
ても、吸着能力の低下は殆んど見られない。この場合、
０．０１規定未満の鉱貨ではアクチニド元素の脱ｉは充
分でなく、また０、５規定を越える鉱νではいたずらに
貴を消費するだけであり、得策でない。従って。In the method of the present invention, actinide elements in wastewater can be sufficiently adsorbed and removed even at an Sv value that is approximately 10 times higher than that of conventional ion exchange resin adsorption methods and chelate resin adsorption methods. In the method of the present invention, the Sv value is 300 h.
-', as shown in Figure 1, the removal rate of actinide elements begins to decrease, and if the Sv value is less than 30h, although sufficient removal is possible, the wastewater treatment efficiency decreases, so it is unsuitable. . That is, in the method of the present invention, the Sv value needs to be in the range of 30 to 300 h from an industrial perspective.
Preferably it is in the range of 50 to 200 hours. In addition, in the method of the present invention, the regeneration of the immobilized tandino-based adsorbent is 0.
Adsorbed actinide elements can be easily desorbed with dilute mineral acids (dilute nitric acid, dilute C acid) of 0.01 to 0.5N. Second
As shown in the figure, almost no decrease in adsorption capacity was observed even after the adsorbent was used 10 times. in this case,
If the ore value is less than 0.01N, the actinide elements will not be removed sufficiently, and if the ore value is more than 0.5N, the precious metal will be wasted, which is not a good idea. Therefore.
本発明方法において脱着に使用される鉱酸の１度は０．
０１〜０．５規定の範囲であり、好ましくは０、Ｏ２Ｎ
２．０７規定の範囲である。このように、本発明方法で
は使用する固定タンニン系吸着体自体が安価であり、吸
着効率は極めて高くかつ脱着も容易であるので、その経
済的効果は大である。The mineral acid used for desorption in the method of the invention has a degree of 0.
01 to 0.5 normal, preferably 0, O2N
2.07 is within the range specified. As described above, in the method of the present invention, the fixed tannin adsorbent itself used is inexpensive, the adsorption efficiency is extremely high, and desorption is easy, so the economic effect is large.
また、従来方法では、アクチニド元素の吸着除去が困難
とされているｐＨが８以上の廃水及び比較的多量の共存
塩を含んでいる廃水においても、本発明方法によれば、
光分にアクチニド元素の吸着除去が可能となる。例えば
原子燃料７Ｊｎ工施設のプロセス廃液は一般にｐＨ８以
上のアルカリ側であるが、本発明方法では、第３図に示
すように％ｐＨ６，２〜１Ｏ０５の範囲で充分にアクチ
ニド元素を吸着除去できる。In addition, according to the method of the present invention, even in wastewater with a pH of 8 or more and wastewater containing a relatively large amount of coexisting salts, where it is difficult to adsorb and remove actinide elements using conventional methods,
Actinide elements can be adsorbed and removed by light. For example, process waste liquid from nuclear fuel 7Jn construction facilities is generally alkaline with a pH of 8 or more, but in the method of the present invention, actinide elements can be sufficiently adsorbed and removed within the range of % pH 6.2 to 1005, as shown in FIG.
次に、本発明を実施例によって、さらに具体的に説明す
るが、以下の実施例は本分明の範囲を限定するものでは
ないう
実施例１
内径１．０ＣＭ、高さ１０．５ｃｍのカラムに固定化柿
渋タンニンを乾量で０．５９尤ｊｌＡし、ｐｉ−１＝９
．８で８ ｆ５ ｐｐｍのウランを含む廃水を５Ｖ＝１
８５ｈ″″→５．６２流して吸着させた。処理後の該廃
水におけるウラン濃度を測定した結果、４．３ ｐｐｍ
であり、ウラン除去率は９５％であった。Next, the present invention will be explained in more detail with reference to Examples, but the following Examples are not intended to limit the scope of the present invention. The dry amount of immobilized persimmon tannin is 0.59 YlA, pi-1 = 9
．． 5V = 1 wastewater containing 8 f5 ppm uranium
85h''''→5.62 hours to adsorb. As a result of measuring the uranium concentration in the wastewater after treatment, it was found to be 4.3 ppm.
The uranium removal rate was 95%.
次いで、純水で充分吸着体を洗浄した後、０．０２規定
の希硝酸を上記カラムに通液し、ウランを脱着したとこ
ろ、９９．８％のウランが脱着により回収された。Next, after thoroughly washing the adsorbent with pure water, 0.02 N dilute nitric acid was passed through the column to desorb uranium, and 99.8% of uranium was recovered by desorption.
実施例２
内径１．０ｃＩｒＬ、高さ１０．５ｃＩｒＬのカラムに
固定化五倍子タンニンを乾量で０，６ｇ充填し、ｐｔ（
＝８．２で６５ｐｐｍのトリウムを含む廃水をＳ Ｖ＝
５５ｈ−’で７１流し、吸着させた。処理後の廃水に
おけるトリウム濃度を測定した結果、１．３ ｐｐｍで
あり、その除去率は９８％であった。Example 2 A column with an inner diameter of 1.0 cIrL and a height of 10.5 cIrL was filled with 0.6 g of immobilized fivefold tannin in dry weight.
= 8.2 and wastewater containing 65 ppm thorium is S V =
71 at 55 h-' to adsorb. As a result of measuring the thorium concentration in the wastewater after treatment, it was found to be 1.3 ppm, and the removal rate was 98%.
次いで、純水で吸着体を洗浄した後０．０５規定の希硫
酸をカラムに通液したところ、吸着したトリウムの９９
．９％が脱着により回収された。Next, after washing the adsorbent with pure water, 0.05 N dilute sulfuric acid was passed through the column, and 99% of the adsorbed thorium was
．． 9% was recovered by desorption.
実施例３
内径１．０！、高さ１０．５（１ｍのカラムに固定化五
倍子タンニンを乾量で０．６ｇ充填し、ｐＦ（＝７．５
’ｔ’ １ （１０ｐｐｂ＋７） ’） ラフ ヲ含ｂ
ｍ水ｔ’ Ｓ Ｖ＝ ７０ｈ−１で、２４．６Ａ通液し
、処理後の廃水におけるウラン礎度を測定した結果、３
ｐｐｂであり、ウラン除去率は９７％であった。Example 3 Inner diameter 1.0! , height 10.5 (1 m) column was filled with 0.6 g of immobilized five-fold tannin in dry weight, pF (=7.5
't' 1 (10ppb+7) ') Rough wo including b
As a result of passing 24.6 A of water at m water t' S V = 70 h-1 and measuring the uranium content in the treated wastewater, it was found that 3
ppb, and the uranium removal rate was 97%.
更に、純水で吸着体を洗浄したｖｋｏ、０７規定の希硫
酸をカラムに通液してウランを脱着させたところ、吸着
したウランの９９．９９６が回収された。Further, when the adsorbent was washed with pure water and uranium was desorbed by passing 07N dilute sulfuric acid through the column, 99.996 of the adsorbed uranium was recovered.
（発明の効果）
本発明は上記のように１吸着体として固定化タンニン系
吸着体を使用することＫよって次の効果を示すものであ
る。(Effects of the Invention) The present invention exhibits the following effects by using an immobilized tannin adsorbent as one adsorbent as described above.
（１） 従来方法に比して放射性廃水処理能力を大幅
に増進する。(1) Significantly improve radioactive wastewater treatment capacity compared to conventional methods.
（２）従来方法で困難とされていたアルカリ性廃水にお
いても、アクチニド元素を光分く除去することができる
。(2) Actinide elements can be removed optically even in alkaline wastewater, which has been difficult to do using conventional methods.
＋３） 固定化タンニンは安価であり、かつ繰返し使
用が可能である。従って、＋１３． ＋２）の効果と相
俟って経済的効果は大きい。+3) Fixed tannins are inexpensive and can be used repeatedly. Therefore, +13. Combined with the effect of +2), the economic effect is large.
（４）使用済吸着体については、容易に焼却ができるの
で放射性固体廃棄物の発生量は極めて少ない。(4) Since used adsorbents can be easily incinerated, the amount of radioactive solid waste generated is extremely small.
第１図は放射性廃水のカラム通液のＳｖ値とアクチニド
元素除去率との関係を示すグラフ図、第２図は吸脱着サ
イクルの繰返し回数とアクチニド元素除去率との関係を
示すグラフ図、第３図は放射性廃水のｐＨとアクチニド
元素除去率との関係を示すグラフ図である。Figure 1 is a graph showing the relationship between the Sv value of radioactive wastewater flowing through the column and the actinide element removal rate. Figure 2 is a graph showing the relationship between the number of adsorption/desorption cycle repetitions and the actinide element removal rate. FIG. 3 is a graph showing the relationship between the pH of radioactive wastewater and the actinide element removal rate.
Claims (4)
いて、固定化タンニン系吸着体を固定層カラムに充填し
、該吸着体の単位量に対する１時間当りの該放射性廃水
通水量（Ｓ．Ｖ．値）を３０〜３００＾ｈ＾−＾１とす
ることを特徴とする放射性廃水の処理方法(1) In a method for treating radioactive wastewater containing actinide elements, a fixed bed column is packed with an immobilized tannin-based adsorbent, and the amount of water flowing through the radioactive wastewater per hour per unit amount of the adsorbent (S.V. ) is 30 to 300^h^-^1.
方法であつて、前記固定化タンニン系吸着体に吸着され
たアクチニド元素を０．０１〜０．５規定の硝酸または
硫酸で脱着し、該固定化タンニン系吸着体を繰返し使用
することを特徴とする処理方法。(2) A method for treating radioactive wastewater according to claim 1, wherein actinide elements adsorbed on the immobilized tannin-based adsorbent are desorbed with 0.01 to 0.5N nitric acid or sulfuric acid. A treatment method characterized by repeatedly using the immobilized tannin-based adsorbent.
方法であつて、前記放射性廃水のｐＨは６．２〜１０．
５の範囲であることを特徴とする処理方法。(3) The method for treating radioactive wastewater according to claim 1, wherein the radioactive wastewater has a pH of 6.2 to 10.
A processing method characterized in that the range is 5.
方法であつて、前記アクチニド元素はウラン、トリウム
またはプルトニウムであることを特徴とする処理方法。(4) The method for treating radioactive wastewater according to claim 1, wherein the actinide element is uranium, thorium, or plutonium.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8367487A JPS63248491A (en) | 1987-04-04 | 1987-04-04 | Treatment of waste water containing actinide element |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8367487A JPS63248491A (en) | 1987-04-04 | 1987-04-04 | Treatment of waste water containing actinide element |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63248491A true JPS63248491A (en) | 1988-10-14 |
| JPH0335997B2 JPH0335997B2 (en) | 1991-05-30 |
Family
ID=13809030
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8367487A Granted JPS63248491A (en) | 1987-04-04 | 1987-04-04 | Treatment of waste water containing actinide element |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63248491A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5158711A (en) * | 1990-01-09 | 1992-10-27 | Mitsubishi Nuclear Fuel Co. | Insoluble tannin preparation process, waste treatment process employing insoluble tannin and adsorption process using tannin |
| EP0530118A2 (en) * | 1991-08-23 | 1993-03-03 | Mitsubishi Nuclear Fuel Company, Ltd. | Method for adsorbing and separating heavy metal elements by using a tannin adsorbent and method of regenerating the adsorbent |
| FR2759196A1 (en) * | 1997-02-04 | 1998-08-07 | Doryokuro Kakunenryo | APPARATUS USING TANNIN FOR THE TREATMENT OF AN EFFLUENT CONTAINING PLUTONIUM |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4874661B2 (en) | 2006-01-30 | 2012-02-15 | 愛知機械工業株式会社 | transmission |
-
1987
- 1987-04-04 JP JP8367487A patent/JPS63248491A/en active Granted
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5158711A (en) * | 1990-01-09 | 1992-10-27 | Mitsubishi Nuclear Fuel Co. | Insoluble tannin preparation process, waste treatment process employing insoluble tannin and adsorption process using tannin |
| EP0530118A2 (en) * | 1991-08-23 | 1993-03-03 | Mitsubishi Nuclear Fuel Company, Ltd. | Method for adsorbing and separating heavy metal elements by using a tannin adsorbent and method of regenerating the adsorbent |
| AU644972B2 (en) * | 1991-08-23 | 1993-12-23 | Mitsubishi Nuclear Fuel Company, Ltd. | Method for adsorbing and separating heavy metal elements by using a tannin adsorbent and method of regenerating the adsorbent |
| FR2759196A1 (en) * | 1997-02-04 | 1998-08-07 | Doryokuro Kakunenryo | APPARATUS USING TANNIN FOR THE TREATMENT OF AN EFFLUENT CONTAINING PLUTONIUM |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0335997B2 (en) | 1991-05-30 |
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