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 |
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JPH0335997B2 (en) | 1991-05-30 |
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