JPH03189599A - Desalting system of nuclear power plant - Google Patents
Desalting system of nuclear power plantInfo
- Publication number
- JPH03189599A JPH03189599A JP1328484A JP32848489A JPH03189599A JP H03189599 A JPH03189599 A JP H03189599A JP 1328484 A JP1328484 A JP 1328484A JP 32848489 A JP32848489 A JP 32848489A JP H03189599 A JPH03189599 A JP H03189599A
- Authority
- JP
- Japan
- Prior art keywords
- acid
- nuclear power
- power plant
- waste
- exchange resin
- 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
- 238000011033 desalting Methods 0.000 title 1
- 239000002253 acid Substances 0.000 claims abstract description 23
- 230000008929 regeneration Effects 0.000 claims abstract description 14
- 238000011069 regeneration method Methods 0.000 claims abstract description 14
- 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 claims abstract description 13
- 239000003513 alkali Substances 0.000 claims abstract description 12
- 239000003456 ion exchange resin Substances 0.000 claims abstract description 11
- 229920003303 ion-exchange polymer Polymers 0.000 claims abstract description 11
- 239000002351 wastewater Substances 0.000 claims abstract description 9
- 239000007788 liquid Substances 0.000 claims description 8
- 238000010612 desalination reaction Methods 0.000 claims description 7
- 239000012535 impurity Substances 0.000 claims description 5
- 238000011084 recovery Methods 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract description 11
- 229910017604 nitric acid Inorganic materials 0.000 abstract description 11
- 239000002699 waste material Substances 0.000 abstract description 11
- 239000002901 radioactive waste Substances 0.000 abstract description 6
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 abstract description 4
- 239000003729 cation exchange resin Substances 0.000 abstract description 4
- 238000004821 distillation Methods 0.000 abstract description 4
- 239000003957 anion exchange resin Substances 0.000 abstract description 3
- 229910021529 ammonia Inorganic materials 0.000 abstract description 2
- 230000007774 longterm Effects 0.000 abstract description 2
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 abstract 12
- 235000006408 oxalic acid Nutrition 0.000 abstract 4
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 230000007850 degeneration Effects 0.000 abstract 1
- QTBSBXVTEAMEQO-UHFFFAOYSA-N Acetic acid Chemical compound CC(O)=O QTBSBXVTEAMEQO-UHFFFAOYSA-N 0.000 description 6
- 230000000694 effects Effects 0.000 description 6
- VEXZGXHMUGYJMC-UHFFFAOYSA-N Hydrochloric acid Chemical compound Cl VEXZGXHMUGYJMC-UHFFFAOYSA-N 0.000 description 4
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 4
- 150000007513 acids Chemical class 0.000 description 4
- 229910052938 sodium sulfate Inorganic materials 0.000 description 4
- 235000011152 sodium sulphate Nutrition 0.000 description 4
- 239000007787 solid Substances 0.000 description 4
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- QAOWNCQODCNURD-UHFFFAOYSA-N Sulfuric acid Chemical compound OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 description 2
- 238000000354 decomposition reaction Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- BDAGIHXWWSANSR-UHFFFAOYSA-N methanoic acid Natural products OC=O BDAGIHXWWSANSR-UHFFFAOYSA-N 0.000 description 2
- 238000000926 separation method Methods 0.000 description 2
- OSWFIVFLDKOXQC-UHFFFAOYSA-N 4-(3-methoxyphenyl)aniline Chemical compound COC1=CC=CC(C=2C=CC(N)=CC=2)=C1 OSWFIVFLDKOXQC-UHFFFAOYSA-N 0.000 description 1
- 239000003638 chemical reducing agent Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 235000019253 formic acid Nutrition 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000005453 pelletization Methods 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は原子力発電所の脱塩システムにおいて再生によ
る二次廃棄物発生量を著しく減少させるシステムに関す
る。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a system for significantly reducing the amount of secondary waste generated by regeneration in a desalination system of a nuclear power plant.
原子力発電所の復水、廃水などの浄化には、除去性能が
高いことからイオン交換樹脂が用いられている。しかし
、イオン交換樹脂の使用に当たっては、酸やアルカリを
用いた再生が必要となる。Ion exchange resins are used to purify condensate and wastewater from nuclear power plants because of their high removal performance. However, when using an ion exchange resin, it is necessary to regenerate it using an acid or an alkali.
再生では、イオン交換樹脂に吸着した復水、廃水などの
不純物に比べて、多量の酸やアルカリが必要である。現
在、酸として硫酸、アルカリとして水酸化ナトリウムが
用いられているため、再生廃液中には硫酸ナトリウムが
生成する。その量は、イオン交換樹脂に吸着した不純物
の百倍以上となる。Regeneration requires a large amount of acid or alkali compared to impurities such as condensate and wastewater adsorbed on the ion exchange resin. Currently, sulfuric acid is used as the acid and sodium hydroxide is used as the alkali, so sodium sulfate is produced in the recycled waste liquid. The amount is more than 100 times that of impurities adsorbed on the ion exchange resin.
硫酸ナトリウムは２０ｗｔ％の溶液となっているため、
特開昭５７−１９７５００号公報などに示されているよ
うに、廃液を硫酸ナトリウムの乾燥粉末とし、さらに、
ペレット化して固化する方法がある。Since sodium sulfate is a 20wt% solution,
As shown in JP-A-57-197500, etc., the waste liquid is made into a dry powder of sodium sulfate, and further,
There is a method of pelletizing and solidifying it.
この方法では水分がなくなるため、硫酸ナトリウムの体
積分となる。This method eliminates water, resulting in the volume of sodium sulfate.
上記の従来技術は、再生に用いられた酸、アルカリを回
収、または、除去することが考えられていないため、二
次廃棄物量の大幅な減容ができないという問題があった
。従って、原子力発電所内に保管できず、放射性廃棄物
として陸地処分が行なわれる。The above-mentioned conventional technology has a problem in that it is not possible to significantly reduce the amount of secondary waste because it does not consider recovering or removing acids and alkalis used for regeneration. Therefore, it cannot be stored inside a nuclear power plant and is disposed of on land as radioactive waste.
本発明の目的は、酸、アルカリを回収することによって
、大幅な減容を可能として、放射性廃棄物の原子力発電
所内での保管管理を可能とすることにある。原子力発電
所の寿命は三十年以上であり、保管・管理の期間内に廃
棄物中に含まれている８ ０ ＣＯ（半減期５ｙ）、”
Ｍｎ （３００ｄ）などの放射性物質の放射能減衰があ
る。これによって、廃棄物中の放射能が少なくなり、ハ
ンドリング等が容易となる。An object of the present invention is to enable significant volume reduction by recovering acids and alkalis, and to enable storage management of radioactive waste within nuclear power plants. The lifespan of a nuclear power plant is over 30 years, and during the period of storage and management, 80 CO (half-life 5 years) is contained in the waste.
There is a radioactive decay of radioactive substances such as Mn (300d). This reduces radioactivity in the waste, making handling easier.
上記の目的を達成するために、本発明は原子力発電所の
脱塩システムが、少なくとも、廃水中から不純物を除去
するイオン交換樹脂の充填塔と、気化性の酸を用いる再
生手段と、気化性の酸を回収する手段と、酸回収後の残
留液を減容して貯蔵する手段とから構成される。To achieve the above object, the present invention provides a desalination system for a nuclear power plant that includes at least a packed column of ion exchange resin for removing impurities from wastewater, a regeneration means using a vaporizable acid, and a desalination system for a nuclear power plant. It consists of a means for recovering the acid, and a means for reducing the volume of the residual liquid after recovering the acid and storing it.
さらに、上記の目的を達成するために、本発明は原子力
発電所の脱塩システムが、少なくとも、廃水中から不純
物を除去するイオン交換樹脂の充填塔と、気化性のアル
カリを用いる再生手段と、気化性のアルカリを回収する
手段と、アルカリ回収後の残留を減容して貯蔵する手段
とから構成される。Furthermore, in order to achieve the above object, the present invention provides a desalination system for a nuclear power plant that includes at least a column packed with an ion exchange resin for removing impurities from wastewater, and a regeneration means using a vaporizable alkali. It consists of a means for recovering vaporizable alkali and a means for reducing the volume and storing the residue after alkali recovery.
気化性の酸、アルカリを使用することによって、蓄留な
どの操作で酸、アルカリの回収が可能となる。それによ
って、残留液の減容が可能となり、原子力発電所内での
長期保管ができる。By using volatile acids and alkalis, it becomes possible to recover them through storage and other operations. This makes it possible to reduce the volume of the residual liquid and enable long-term storage within the nuclear power plant.
以下、本発明の一実施例を第１図により説明する。ここ
では、陽イオン交換樹脂のみで廃水を処理し、蒸発性の
酸として硝酸を用いた場合について述べる。図中で、１
は充填塔、２は酸タンク、３は蒸留濃縮器、４は凝縮器
、５は貯槽、６ないし１０はバルブである。充填塔１は
バルブ６．８を開き、バルブ７．９を閉じて廃水の浄化
を行なう。次いで、バルブ６．８を閉じ、バルブ７．９
を開いて、酸タンク２より硝酸（約２Ｎ）を充填塔１に
流し、イオン交換樹脂を再生する。硝酸は蒸留濃縮器３
に送られ、加熱される。加熱によって硝酸は蒸圧となっ
て凝縮器４に流れ、ここで硝酸の溶液となる。硝酸溶液
は酸タンク２に送られ、再利用される。残留物はバルブ
１０を通り、貯槽に貯えられる。An embodiment of the present invention will be described below with reference to FIG. Here, we will discuss the case where wastewater is treated only with a cation exchange resin and nitric acid is used as the evaporative acid. In the diagram, 1
2 is a packed column, 2 is an acid tank, 3 is a distillation concentrator, 4 is a condenser, 5 is a storage tank, and 6 to 10 are valves. The packed column 1 opens valve 6.8 and closes valve 7.9 to purify the waste water. Valve 6.8 is then closed and valve 7.9 is closed.
is opened and nitric acid (approximately 2N) is poured into the packed tower 1 from the acid tank 2 to regenerate the ion exchange resin. Distillation concentrator 3 for nitric acid
and heated. By heating, the nitric acid becomes vapor pressure and flows into the condenser 4, where it becomes a solution of nitric acid. The nitric acid solution is sent to acid tank 2 and reused. The residue passes through valve 10 and is stored in a reservoir.
本実施例によれば、再生による放射性廃棄物の体積を大
幅に減容することができ、原子力発電所運転中（三十年
以上）の廃棄物の貯蔵が可能となる。According to this embodiment, the volume of radioactive waste due to regeneration can be significantly reduced, and the waste can be stored while the nuclear power plant is in operation (for more than 30 years).
上記実施例は、陽イオン交換樹脂の例であるが、陰イオ
ン交換樹脂の場合も、気化性のアルカリとしてアンモニ
アを用いて、第１図と同様に処理することができる。ま
た、陽イオン交換樹脂と陰イオン交換樹脂を混合して用
いる場合には、再生操作の前に通常行なわれる分離操作
が必要になるが、その後は酸、アルカリに対して、それ
ぞれ、第１図の操作を行なうことによって同様の効果を
奏する。Although the above embodiment is an example of a cation exchange resin, an anion exchange resin can also be treated in the same manner as shown in FIG. 1 using ammonia as a vaporizable alkali. In addition, when using a mixture of cation exchange resin and anion exchange resin, a separation operation that is normally performed before the regeneration operation is required, but after that, it is necessary to perform the separation operation that is normally performed before the regeneration operation. Similar effects can be obtained by performing the following operations.
また、実施例では、気化性の酸として硝酸を用いたが、
塩酸、酢酸などの酸も用いることもできるが、塩酸の場
合、腐蝕の点から問題があり、酢酸では弱酸であるため
再生効率が悪くなる。In addition, in the examples, nitric acid was used as the volatile acid, but
Acids such as hydrochloric acid and acetic acid can also be used, but hydrochloric acid poses a problem in terms of corrosion, while acetic acid is a weak acid and therefore has poor regeneration efficiency.
また、この実施例では、液体のまま残留物の貯槽に貯蔵
したが、固形の容器（２００Ｑドラ４缶程度）の内に固
体の塊として固化する方式がある。Further, in this example, the residue was stored as a liquid in the residue storage tank, but there is a method in which the residue is solidified as a solid lump in a solid container (about four 200Q drums).
これは容器を側面や下面より加熱し、内部に廃液をゆっ
くり滴下するもので、固体の塊となる。これによって、
さらに減容効果が高められ、本発明の効果がよく現われ
る。This heats the container from the sides and bottom and slowly drips the waste liquid inside, forming a solid mass. by this,
Furthermore, the volume reduction effect is enhanced, and the effects of the present invention are clearly exhibited.
さらに、固体の塊として貯蔵する際に、硝酸再生の残留
物中にギ酸など還元性物質（還元によって生成した分解
物がガス化するものが効果的）で蒸留濃縮によって回収
できなかった硝酸を分解することができる。これによっ
て減容効果と、爆発性の物質を作りやすい硝酸の完全分
解が可能となる。Furthermore, when stored as a solid mass, the nitric acid that could not be recovered by distillation and concentration is decomposed using a reducing substance such as formic acid (effective is one that gasifies the decomposition products produced by reduction) in the residue of nitric acid regeneration. can do. This allows for a volume reduction effect and complete decomposition of nitric acid, which tends to produce explosive substances.
本発明によれば、再生によって発生する放射性廃棄物の
大幅な減容を可能とし、原子力発電所運転中三十年以上
の間、放射性廃棄物の保管管理が可能となる。この保管
管理によって廃棄物中に含まれる放射性物質は、減衰に
よって少なくすることができる。According to the present invention, it is possible to significantly reduce the volume of radioactive waste generated through regeneration, and it is possible to store and manage radioactive waste for more than 30 years while a nuclear power plant is in operation. Through this storage management, the amount of radioactive materials contained in waste can be reduced through attenuation.
第１図は本発明の一実施例を示すフローチャート図であ
る。
■・・・イオン交換樹脂の充填塔、２・・酸タンク、３
・蒸発濃縮器、５・・・貯蔵。FIG. 1 is a flowchart showing one embodiment of the present invention. ■... Ion exchange resin packed tower, 2... Acid tank, 3
- Evaporative concentrator, 5...Storage.
Claims (1)
水純物を除去するイオン交換樹脂の充填塔と、気化性の
酸を用いる再生手段と、気化性の酸を回収する手段と、
酸回収後の残留液を減容して貯蔵する手段とを含む原子
力発電所の脱塩システム。 ２、原子力発電所の脱塩システムにおいて、廃水中から
不純物を除去する前記イオン交換樹脂の前記充填塔と、
気化性のアルカリを用いる前記再生手段と、気化性のア
ルカリを回収する手段と、アルカリ回収後の残留液を減
容して貯蔵する手段とからなる原子力発電所の脱塩シス
テム。[Claims] 1. In a desalination system for a nuclear power plant, a packed column of ion exchange resin for removing water purity from wastewater, a regeneration means using a volatile acid, and a recovery means for recovering the volatile acid and the means to
and means for reducing and storing residual liquid after acid recovery. 2. In a desalination system of a nuclear power plant, the packed column of the ion exchange resin removes impurities from wastewater;
A desalination system for a nuclear power plant, comprising the regeneration means using vaporizable alkali, means for recovering vaporizable alkali, and means for reducing and storing residual liquid after alkali recovery.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1328484A JPH03189599A (en) | 1989-12-20 | 1989-12-20 | Desalting system of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1328484A JPH03189599A (en) | 1989-12-20 | 1989-12-20 | Desalting system of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03189599A true JPH03189599A (en) | 1991-08-19 |
Family
ID=18210791
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1328484A Pending JPH03189599A (en) | 1989-12-20 | 1989-12-20 | Desalting system of nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03189599A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008238113A (en) * | 2007-03-28 | 2008-10-09 | Mitsubishi Heavy Ind Ltd | Co2 recovery apparatus and waste treatment method |
| CN107195352A (en) * | 2017-05-24 | 2017-09-22 | 中国核电工程有限公司 | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system |
-
1989
- 1989-12-20 JP JP1328484A patent/JPH03189599A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008238113A (en) * | 2007-03-28 | 2008-10-09 | Mitsubishi Heavy Ind Ltd | Co2 recovery apparatus and waste treatment method |
| CN107195352A (en) * | 2017-05-24 | 2017-09-22 | 中国核电工程有限公司 | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system |
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