JPS5892997A - Condensed water clean-up device - Google Patents
Condensed water clean-up deviceInfo
- Publication number
- JPS5892997A JPS5892997A JP56190536A JP19053681A JPS5892997A JP S5892997 A JPS5892997 A JP S5892997A JP 56190536 A JP56190536 A JP 56190536A JP 19053681 A JP19053681 A JP 19053681A JP S5892997 A JPS5892997 A JP S5892997A
- Authority
- JP
- Japan
- Prior art keywords
- condensate
- purification
- filter
- circulation pump
- demineralizer
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 24
- 238000000746 purification Methods 0.000 claims description 39
- 238000009835 boiling Methods 0.000 claims description 3
- 238000011144 upstream manufacturing Methods 0.000 claims description 3
- 150000003839 salts Chemical class 0.000 claims 1
- 238000012423 maintenance Methods 0.000 description 6
- 238000007689 inspection Methods 0.000 description 5
- 239000012857 radioactive material Substances 0.000 description 5
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 230000000737 periodic effect Effects 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000005115 demineralization Methods 0.000 description 1
- 230000002328 demineralizing effect Effects 0.000 description 1
- 238000000151 deposition Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Water Treatment By Sorption (AREA)
- Separation Using Semi-Permeable Membranes (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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
発明の技術分野
本発＠ｊ４Ｆｉ放射能を有する蒸気を使用する沸騰水形
原子力発電所のタービン設備６二おける復水浄化循環ポ
ンプの放射能汚染を低減させる含水浄化装ｆｌ１１ｃ関
する。Detailed Description of the Invention Technical Field of the Invention Hydrous purification system for reducing radioactive contamination of a condensate purification circulation pump in turbine equipment 62 of a boiling water nuclear power plant using steam with radioactivity Regarding fl11c.
発明の技術的背景
従来、沸騰水形原子力発電所Ｉ：おいては、第１図響二
示すよう響二、原子炉（１）で発生した蒸気は主蒸気管
（２）を通り、高圧タービン（３）、湿分分離器（４）
及び低圧タービン（６）を経て、王復水勧（１）に導か
れ凝縮して復水となる。また一部の蒸気は図示しない経
路Ｃ二より高圧給水加熱器（））及び低圧給水加熱益（
８）吟で給水を昇温した後、復水となりドレン管（９）
を経て主復水器（６）導かれるものもある。Technical Background of the Invention Conventionally, in a boiling water nuclear power plant I, as shown in Figure 1, the steam generated in the nuclear reactor (1) passes through the main steam pipe (2) and is transferred to the high-pressure turbine. (3), moisture separator (4)
After passing through a low pressure turbine (6), the water is led to a condensate water pipe (1) where it condenses and becomes condensate. In addition, some of the steam is transferred from path C2 (not shown) to the high pressure feed water heater ()) and the low pressure feed water heating heater (
8) After raising the temperature of the water supply with Gin, it becomes condensed water and drains into the drain pipe (9)
Some are led to the main condenser (6) via the .
主復水［６（６’） ｌ；は復水ｔ−浄化するための復
水浄化装置（至）が設置されている。この従来の復水浄
化懺 ′電輪は、主復水＠ （６）出口から順次、
復水浄化ポンプ（１０ａ） 、復水ｒ過器（１０ｂ）及
び復水脱塩器（１０ｃ）へと接続されている。A condensate purification device (to) is installed for the main condensate [6 (6') l; to purify the condensate. This conventional condensate purification system's electric wheels are sequentially operated from the main condensate @ (6) outlet.
It is connected to a condensate purification pump (10a), a condensate filter (10b) and a condensate demineralizer (10c).
主復水器（６）から出た復水け、との復水浄化ポンプで
原子炉（１）への給水として十分な水質１二処理されだ
後、蒸気式空気抽出器中間冷却器（６）及びグランド蒸
気復水器（２）を通って再び主復水器（６）へ戻る。After the condensate discharged from the main condenser (6) has been treated with a condensate purification pump to a sufficient quality for supplying water to the reactor (1), the steam air extractor intercooler (6) ) and the grand steam condenser (2) and returns to the main condenser (6).
この彼、復水ポンプ（至）で昇圧され、低圧給水加熱４
（ｌｉｔで給水温度を上げ、原子炉給水ポンプに）を
経て、史に高圧給水加熱器（７）で昇温され、給水管（
２））から原子炉（１）へ給水される。This pressure is increased by the condensate pump (towards), and low-pressure feed water is heated 4
(raise the temperature of the feed water with lit and send it to the reactor feed water pump), then the temperature is raised in the high pressure feed water heater (7), and then the feed water pipe (
2)) Water is supplied to the reactor (1).
復水浄化製置ｔＩＡでは、復水１過器（１０ｂ）及び復
水脱塩器（１０ｃ） −二て後水中の核分裂生成物や腐
食生成＃ｍ等の放射性＠質を除去すると共に、万一、土
憤水器（６）で復水中晶二海水が漏洩した場合でも、復
水脱塩器（１０ｃ） にて復水中の塩素イオン濃度を低
減し、原子炉（１）への給水として十分な水質を保つよ
う６二なされてし）る。In the condensate purification plant tIA, the first condensate filter (10b) and the condensate demineralizer (10c) are used to remove radioactive materials such as fission products and corrosion products #m in the water, and to 1. Even if condensate crystalline seawater leaks from the soil condenser (6), the condensate desalination device (10c) reduces the chlorine ion concentration in the condensate and supplies water to the reactor (1). Measures are taken to maintain adequate water quality.
背景技術の間醜点
従って、復水ｆ過器（１０ｂ）及び復水脱塩器（１０ｃ
）の上流側の配管や機器を流れる復水＃′ｉ、放射性物
質が除去される前の復水である。このため、特番二伽水
浄化循環ポンプ（１０ａ）やその周辺の配管に付＊Ｓる
いは沈着する放射性物質が多く、これらの周辺の放射線
量率が高くなるので、原子炉停止後の定期検査や保修時
の作業員の被曝線量が増加する。近年、原子力発電所の
増加や運転期間の増加により、定期検査や保修時の総被
曝線賃が増加しており、各作業時の被曝線量の低減化が
望まれている。 ゛
発明の目的
本発明は復水浄化循環ポンプとその周辺の配管の定期検
査や保修時の作業員の放射線被曝を低減させる復水浄化
製置を提供することを目的とする。The disadvantages of the background art are therefore that the condensate filter (10b) and the condensate demineralizer (10c)
Condensate #'i flowing through piping and equipment upstream of ) is condensate before radioactive materials are removed. For this reason, there is a lot of radioactive material attached to or deposited on the special number Nika Water Purification Circulation Pump (10a) and the piping around it, and the radiation dose rate in these areas increases, so regular inspections after the reactor shut down are necessary. The radiation dose for workers during maintenance and maintenance will increase. In recent years, due to the increase in the number of nuclear power plants and the increase in operating periods, the total radiation exposure cost during periodic inspections and maintenance has increased, and there is a desire to reduce the radiation dose during each work. [Object of the Invention] An object of the present invention is to provide a condensate purification system that reduces radiation exposure of workers during periodic inspection and maintenance of a condensate purification circulation pump and its surrounding piping.
発明の概費
本発明Ｉ：おいては、復水浄化循環ポンプを復水を過器
より下流側に配設し、復水浄化循環ポンプおよびその周
辺の配管の放射能を低減する。Outline of the Invention In the present invention I, the condensate purification circulation pump is disposed downstream of the condensate filter to reduce the radioactivity of the condensate purification circulation pump and the piping around it.
発明の実施例
実施例１
以下、第２図を参照して本発明の第１の実施例を説明す
る。第２要において、主復水器（６）の出口から順次、
復水な浄化するための復水濾過器（１０ｂ）および復水
脱塩器（１０ａ）と復水を循環させるための復水浄化循
環ポンプ（１０ａ）を設置した復水浄化装置ｌｉｔ明と
する。（１１） 、四はり水浄化装置−から復水を送込
まれる次段の蒸気式空気抽出器中間冷却器とグランド蒸
気復水器である。この復水浄化装置−を用いる他のター
ビン設備は図示しないが、第１図５二示したタービン設
備と同様である。EMBODIMENTS OF THE INVENTION Example 1 A first example of the present invention will be described below with reference to FIG. At the second point, sequentially from the outlet of the main condenser (6),
A condensate purification device equipped with a condensate filter (10b) and a condensate demineralizer (10a) for purifying condensate and a condensate purification circulation pump (10a) for circulating condensate. . (11) The next stage steam type air extractor intercooler and the grand steam condenser receive condensate from the four-barrel water purification device. Although other turbine equipment using this condensate purification device is not shown, it is similar to the turbine equipment shown in FIG. 1, 5-2.
゛次纏二作用につ□いて説明する。 ・上記のようぷ
二構成される復水浄化装置（転）では、主復水器（６）
から出た復水け、直ちに復水１遍器・（１０ｂ）及び復
水脱塩器（１０ｃ）により放射性物質を除去した後、復
水浄化循環ポンプ（１０ａ）に至る。Next, the two effects will be explained.・In the condensate purification device (transfer) with the above two configurations, the main condenser (6)
Immediately, radioactive materials are removed from the condensate discharged from the condensate tank (10b) and the condensate demineralizer (10c), and then the condensate is sent to the condensate purification circulation pump (10a).
このため、復水１過器（’１０ｂ）及び復水脱塩器（１
０ｅ）の下流側の機器並びに配管、即ち復水浄化循環ポ
ンプ（１０ａ）とその周辺配管等内を流れる復水の放射
能一度は十分低くなり、第１図に示す従来の復水浄化循
環ポンプ（１０ａ）の位置では、その復水浄化循環ポン
プ（１０ａ）とその周辺配管Ｓ二付着あるいは沈着する
放射性物質の線量率が数ｌＯ〜１００ ミＩＪレントゲ
ン／ ｈｒであったものが、この実施例の位置では数０
．１〜１ミリレントゲン／ ｈｒとなってｈｏｏ程度に
減少する。従って、復水浄化循環ポンプ（１０ａ）およ
びその周辺配管の定期検査や保修時の作業員の放射線被
曝線量は従来の場合に比べてＭｏ□ ＊ Ｈ、：減少す
る。又、従来の復水濾過器（１０ｂ）と復水脱塩器（１
０ｃ）とは復“水浄化循環ポンプ（１０ａ）の下流側に
配装置されてい友ため、復水１過器（１０ｂ）″と＠１
永脱塩赫’（ｉｏｃ）に高圧の復水を通過させること６
二なり圧力損失が大きかったが、本発明Ｃ二よ□れば、
逆の配置としたため、復水濾過器（１０ｂ）と復水脱塩
器（１０ｃ）内を流れる復水な低圧ζニするので圧力損
失が小なく去り効率が向上する。For this reason, a condensate 1-passer ('10b) and a condensate demineralizer (1
The radioactivity of the condensate flowing through the equipment and piping on the downstream side of 0e), that is, the condensate purification circulation pump (10a) and its surrounding piping, becomes sufficiently low, and the conventional condensate purification circulation pump shown in Fig. 1 At the position (10a), the dose rate of the radioactive material adhering to or depositing on the condensate purification circulation pump (10a) and its surrounding piping S2 was several lO to 100 μIJ Roentgen/hr. number 0 at the position
．． It becomes 1 to 1 milliroentgen/hr and decreases to about hoo. Therefore, the radiation exposure dose of workers during periodic inspection and maintenance of the condensate purification circulation pump (10a) and surrounding piping is reduced compared to the conventional case. In addition, a conventional condensate filter (10b) and a condensate demineralizer (1
0c) is located downstream of the condensate water purification circulation pump (10a), so the condensate 1-passer (10b) and @1
Passing high-pressure condensate through permanent demineralization (IOC)6
2, the pressure loss was large, but with the present invention C2,
Since the arrangement is reversed, the condensate flowing through the condensate filter (10b) and the condensate demineralizer (10c) has a low pressure ζ, which reduces pressure loss and improves efficiency.
実施例２゛
＠ａｉｖ己示す第２の実施□例は、主復水器（６）の出
口から順次、復水濾過器（ｉｏｂ） 、復水浄化循環ポ
ンプ（１０ａ） 、復水脱塩器（１０ｃ）と配列して復
水浄化製置四を形成したものであり、他は★施例１と同
様である。Embodiment 2 ゛@aiv The second embodiment □ example shows the steps from the outlet of the main condenser (6) to the condensate filter (iob), the condensate purification circulation pump (10a), and the condensate demineralizer. (10c) was arranged to form a condensate purification station 4, and the rest was the same as in Example 1.
このようにしても、復水は復水１過器（１０ｂ）で大部
分の放射性物質を除去されてしまうので実施例１に準じ
た作用効果を有する。Even in this case, since most of the radioactive substances are removed from the condensate in the condensate single filter (10b), the same effect as in the first embodiment can be obtained.
尚、本発明は上記し、かつ図面に示した実施例のみ−二
限定されるものではなく、その要旨′を変更しない範囲
で、種々変形して実施できることは勿酬である。It should be noted that the present invention is not limited to the embodiments described above and shown in the drawings, but can of course be implemented with various modifications without changing the gist thereof.
発明の効果
以上説明したようＣ二、本発明−二よれば、復水浄化装
置ポンプを復水濾過器より下流側に配設し九ことにより
一復水浄化循環ポンプおよびその周辺の配管の定期点検
や保修時の作業員の放射線被−＊ｉｉを大幅−二減少で
きると共（二、運転時の効率を向上した復水浄化装置を
提供することができる。Effects of the Invention As explained above, according to the present invention-2, the condensate purification device pump is disposed downstream of the condensate filter. It is possible to significantly reduce the radiation exposure of workers during inspection and maintenance, and also to provide a condensate purification device that is more efficient during operation.
第１図は従来の復水浄化装置を備えた原子力発電所のタ
ービン設備を示す系統図、第２図および第３図はそれぞ
れ異なる本発明の復水浄化装置の実施例をその周辺と共
に示す系統図である。
６・−主復水器 ｌＯ・・・復水浄化装置１０ａ
＝・復水浄化循環ポンプ ｌＯ１＋・−復水濾過器１
０ｃ・・・復水脱塩器
１１・・・次段の一つである蒸気式空気抽出器中間冷却
器１２・・・次段の一つであるグランド蒸気復水器第
１ 図
第２図
第 ３ 図FIG. 1 is a system diagram showing turbine equipment of a nuclear power plant equipped with a conventional condensate purification device, and FIGS. 2 and 3 are system diagrams showing different embodiments of the condensate purification device of the present invention together with their surroundings. It is a diagram. 6.-Main condenser lO...Condensate purification device 10a
=・Condensate purification circulation pump lO1+・−Condensate filter 1
0c...Condensate demineralizer 11...Steam air extractor intercooler 12, which is one of the next stages...Grand steam condenser, which is one of the next stages
1 Figure 2 Figure 3
Claims (1)
を備え、沸騰水形態、子力発電所のタービン設備の主復
水器から出た復水を浄化して次段へ送出する復水浄化循
環ボンおいて、復水浄化＊環ポンプを復水Ｆ−Ａｈより
下流匈に配設したことを特徴とする復水浄化装置。 （Ｚ） ＊水の流れの上流餞から、復水＃：ＩｊＭ器
、復水腕塩番、復水浄化循環ポンプのＩＩ薯二配設し九
ことを特徴とする特許請求の範囲第１項記載の復水浄化
装置。 （８） 復水の流れの上流側から、復水濾過凶、復水
浄化循環ポンプ、復水脱塩器の順に配設したことを特徴
とする特許請求の範囲第１項記載の復水浄化装置。[Scope of Claims] (1) It is equipped with a condensate 1 filter, a condensate demineralizer, and a condensate purification circulation tank 1, and the boiling water is discharged from the main condenser of the turbine equipment of the child power plant. A condensate purification device characterized in that a condensate purification*ring pump is disposed downstream of condensate F-Ah in a condensate purification circulation tank that purifies condensate and sends it to the next stage. (Z) *Claim 1 of the first claim is characterized in that a condensate #: IJM device, a condensate arm salt filter, and a condensate purification circulation pump are arranged from the upstream of the water flow. The condensate purification device described. (8) The condensate purification according to claim 1, characterized in that the condensate filter, the condensate purification circulation pump, and the condensate demineralizer are arranged in this order from the upstream side of the condensate flow. Device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56190536A JPS5892997A (en) | 1981-11-30 | 1981-11-30 | Condensed water clean-up device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56190536A JPS5892997A (en) | 1981-11-30 | 1981-11-30 | Condensed water clean-up device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5892997A true JPS5892997A (en) | 1983-06-02 |
Family
ID=16259714
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56190536A Pending JPS5892997A (en) | 1981-11-30 | 1981-11-30 | Condensed water clean-up device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5892997A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6017093U (en) * | 1983-07-11 | 1985-02-05 | 株式会社ケンウッド | Acoustic diaphragm |
| JP2013213474A (en) * | 2012-04-04 | 2013-10-17 | Mitsubishi Heavy Ind Ltd | Power plant |
-
1981
- 1981-11-30 JP JP56190536A patent/JPS5892997A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6017093U (en) * | 1983-07-11 | 1985-02-05 | 株式会社ケンウッド | Acoustic diaphragm |
| JP2013213474A (en) * | 2012-04-04 | 2013-10-17 | Mitsubishi Heavy Ind Ltd | Power plant |
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