JPS58210599A - Method of processing liquid waste from atomic power plant - Google Patents
Method of processing liquid waste from atomic power plantInfo
- Publication number
- JPS58210599A JPS58210599A JP9307982A JP9307982A JPS58210599A JP S58210599 A JPS58210599 A JP S58210599A JP 9307982 A JP9307982 A JP 9307982A JP 9307982 A JP9307982 A JP 9307982A JP S58210599 A JPS58210599 A JP S58210599A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- tritium
- concentration
- storage tank
- high concentration
- 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
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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
本発明は原子力施設から排出されるトリチウム含有廃液
の処理方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for treating tritium-containing waste liquid discharged from a nuclear facility.
原子力施設からの排水のトリチウム除去・回収方法につ
いては、従来から、水精留による方法等実用的な方法が
確立している。Practical methods such as water rectification have been established for removing and recovering tritium from wastewater from nuclear facilities.
しかしながら、これによって回収された高濃度トリチウ
ム廃液の貯蔵については末だ確定的な方法が考えられて
おらず、その貯蔵法の開発が待たれていた。However, no definite method has yet been considered for storing the high-concentration tritium waste liquid recovered, and the development of such a storage method has been awaited.
本発明はこのような問題点を解決し、限られた施設内に
高濃度トリチウム廃液を半永久的に貯蔵できる方法を提
供することを目的とする。An object of the present invention is to solve these problems and provide a method for semi-permanently storing high-concentration tritium waste liquid within a limited facility.
そしてその特徴は高濃度廃液貯槽内で自然崩壊した低濃
度廃液を該トリチウム濃縮装置に再循環して再濃縮し、
高濃度となった廃液を該高濃度廃液貯槽内へ再貯蔵する
こと番特徴とする。The feature is that the low-concentration waste liquid that naturally disintegrates in the high-concentration waste liquid storage tank is recirculated to the tritium concentrator and reconcentrated.
The main feature is that the highly concentrated waste liquid is stored again in the highly concentrated waste liquid storage tank.
以下、本発明の一実施例を図面にもとづいて説明する。Hereinafter, one embodiment of the present invention will be described based on the drawings.
１はトリチウム濃縮装置で原子力施設から排出されるト
リチウム含有廃液は、ここへ供給され、トリチウム分を
濃縮・回収する。 回収された濃縮トリチウム廃液は管
路６を経て、高濃度廃液貯槽２に供給される。 トリ
チウム分が除去された排水は管路４から排出される。1 is a tritium concentrator. Tritium-containing waste liquid discharged from a nuclear facility is supplied to this device, and the tritium content is concentrated and recovered. The collected concentrated tritium waste liquid is supplied to the high concentration waste liquid storage tank 2 through a pipe line 6. The wastewater from which tritium has been removed is discharged from the pipe 4.
２は高濃度廃液貯槽で、濃縮された高濃度トリチラム廃
液が貯蔵されている。 ３は廃液供給設備で、高濃度廃
液貯槽２内に貯槽されている廃液をトリチウム濃縮装置
１に再循環するものである。2 is a high-concentration waste liquid storage tank in which concentrated high-concentration trithiram waste liquid is stored. Reference numeral 3 denotes a waste liquid supply facility that recirculates the waste liquid stored in the high concentration waste liquid storage tank 2 to the tritium concentrator 1.
６．７．８はそれぞれの装置を連結する管路である。6.7.8 is a conduit connecting each device.
原子力施設から排出されるトリチウム含有廃液は管路５
からトリチウム濃縮装置１に供給され、トリチウム分が
除去された排水は管路４から排出される。 濃縮された
側の廃液は管路６から高濃度廃液貯槽２に貯められる。Tritium-containing waste liquid discharged from nuclear facilities is piped into pipe 5.
The waste water is supplied to the tritium concentrator 1 from the drain and is discharged from the pipe 4 from which the tritium content has been removed. The concentrated waste liquid is stored in a high concentration waste liquid storage tank 2 through a pipe 6.
高濃度廃液貯槽２内の廃液中のトリチウムは１２．７
年の半減期で自然崩壊駿、トリチウム濃縮設備出口の管
路６を流れる廃液の濃度よりは少しトリチウム濃度が薄
くなっている。Tritium in the waste liquid in the high concentration waste liquid storage tank 2 is 12.7
The tritium concentration is slightly lower than the concentration of the waste liquid flowing through pipe 6 at the outlet of the tritium concentrating equipment, which naturally decays after a half-life of 20 years.
そこで、管路７を経て廃液供給設備３により液状態ある
いは蒸気状態で管路８を経て、トリチウム濃縮装置１に
再度供給することにより高濃度廃液貯槽１内の液量を増
加させることなく全量を半永久的に貯蔵する。Therefore, by supplying the tritium to the tritium concentrator 1 again in a liquid or vapor state through the pipe 7 and the waste liquid supply equipment 3 through the pipe 8, the total amount of liquid in the high concentration waste liquid storage tank 1 can be removed without increasing the amount of liquid. Store semi-permanently.
具体的に本発明方法の一実施例を述べると、５ｘ１０２
ｃｉ／ｍ″の濃度の排水を５ ？ｄａｙの割合で処理し
、低濃度側の排水濃度を１ ｃ＋／ｍ’ 、高濃度側の
濃度を２Ｘ−１０’ ｃゾ♂まで濃縮し、１０ｍ’の高
濃度廃液貯槽内に貯蔵する場合についての各部の物質の
収支を計算すると次表のようになる。 ただし１年間の
稼動日数は３００日とする。To specifically describe one embodiment of the method of the present invention, 5x102
Treat wastewater with a concentration of ci/m'' at a rate of 5?day, concentrate the wastewater concentration on the low concentration side to 1 c+/m' and the concentration on the high concentration side to 2X-10'c♂, and then 10 m' The balance of materials in each part when stored in a high-concentration waste liquid storage tank is calculated as shown in the table below. However, the number of operating days per year is assumed to be 300.
表
本発明によれば、トリチウム濃縮装置により濃縮された
高濃度トリチウム廃液を高濃度廃液貯槽に貯蔵するが、
トリウムは半減期の周期で自然崩壊するため、多少濃度
の低下した廃液を再度トリチウム濃縮装置に循環し再濃
縮することによって、この系内に半永久的に貯蔵するこ
とが可能となる。Table According to the present invention, the high concentration tritium waste liquid concentrated by the tritium concentrator is stored in the high concentration waste liquid storage tank.
Since thorium naturally decays during its half-life period, it is possible to store the waste liquid semi-permanently in the system by circulating the waste liquid, whose concentration has decreased somewhat, to the tritium concentrator and concentrating it again.
さらにトリチウム含有廃液をトリチウム濃縮装置および
高濃度廃液貯槽を循環させるので、装置が別に必要とし
ないばかりでなく、その酢済的な効果も大きい。Furthermore, since the tritium-containing waste liquid is circulated through the tritium concentrator and the high-concentration waste liquid storage tank, not only is no separate apparatus required, but it is also highly effective as a waste liquid.
第１図は本発明方法の具体的な一実施例を示す図である
。FIG. 1 is a diagram showing a specific embodiment of the method of the present invention.
Claims (1)
ウム濃縮装置に導入してトリチウムを濃縮回収し、高濃
度廃液貯槽内へ貯蔵する処理方法において、 該高濃度廃液貯槽内で自然崩壊した低濃度廃液を該トリ
チウム濃縮装置に再循環して再濃縮し、高濃度となった
廃液を該高濃度廃液貯槽内へ再貯蔵することを特徴とす
る原子力施設から排出される廃液の処理方法。[Scope of Claims] A treatment method in which a tritium-containing waste liquid discharged from a nuclear facility is introduced into a tritium concentrator to concentrate and recover tritium, and stored in a high concentration waste liquid storage tank, which naturally disintegrates in the high concentration waste liquid storage tank. A method for treating waste liquid discharged from a nuclear facility, characterized by recycling the low concentration waste liquid into the tritium concentrator and reconcentrating it, and re-storing the high concentration waste liquid in the high concentration waste liquid storage tank. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9307982A JPS58210599A (en) | 1982-06-02 | 1982-06-02 | Method of processing liquid waste from atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9307982A JPS58210599A (en) | 1982-06-02 | 1982-06-02 | Method of processing liquid waste from atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58210599A true JPS58210599A (en) | 1983-12-07 |
| JPS6348038B2 JPS6348038B2 (en) | 1988-09-27 |
Family
ID=14072506
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9307982A Granted JPS58210599A (en) | 1982-06-02 | 1982-06-02 | Method of processing liquid waste from atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58210599A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2022001887A (en) * | 2015-10-09 | 2022-01-06 | ヴェオリア ニュークリア ソリューションズ インコーポレイテッドVeolia Nuclear Solutions Inc. | Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes |
-
1982
- 1982-06-02 JP JP9307982A patent/JPS58210599A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2022001887A (en) * | 2015-10-09 | 2022-01-06 | ヴェオリア ニュークリア ソリューションズ インコーポレイテッドVeolia Nuclear Solutions Inc. | Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6348038B2 (en) | 1988-09-27 |
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