JPS63259498A - Condensate purifying facility for nuclear power plant - Google Patents
Condensate purifying facility for nuclear power plantInfo
- Publication number
- JPS63259498A JPS63259498A JP62093646A JP9364687A JPS63259498A JP S63259498 A JPS63259498 A JP S63259498A JP 62093646 A JP62093646 A JP 62093646A JP 9364687 A JP9364687 A JP 9364687A JP S63259498 A JPS63259498 A JP S63259498A
- Authority
- JP
- Japan
- Prior art keywords
- condensate
- flow rate
- iron
- filtration device
- outlet
- 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
- 238000001914 filtration Methods 0.000 claims description 46
- 238000010612 desalination reaction Methods 0.000 claims description 37
- 238000000746 purification Methods 0.000 claims description 16
- 239000012528 membrane Substances 0.000 claims description 5
- 238000011084 recovery Methods 0.000 claims 1
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 224
- 229910052742 iron Inorganic materials 0.000 description 112
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 46
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 34
- 238000005253 cladding Methods 0.000 description 31
- 229910017052 cobalt Inorganic materials 0.000 description 17
- 239000010941 cobalt Substances 0.000 description 17
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 17
- 229910052759 nickel Inorganic materials 0.000 description 17
- 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 16
- 239000003456 ion exchange resin Substances 0.000 description 16
- 229920003303 ion-exchange polymer Polymers 0.000 description 16
- 230000002285 radioactive effect Effects 0.000 description 11
- 238000010586 diagram Methods 0.000 description 7
- 230000007423 decrease Effects 0.000 description 6
- 230000005855 radiation Effects 0.000 description 6
- 239000011347 resin Substances 0.000 description 6
- 229920005989 resin Polymers 0.000 description 6
- 239000000470 constituent Substances 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 230000007797 corrosion Effects 0.000 description 4
- 238000005260 corrosion Methods 0.000 description 4
- 230000003247 decreasing effect Effects 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 239000012535 impurity Substances 0.000 description 3
- 238000011144 upstream manufacturing Methods 0.000 description 3
- 150000001768 cations Chemical class 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 230000032683 aging Effects 0.000 description 1
- 150000001450 anions Chemical class 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 229910044991 metal oxide Inorganic materials 0.000 description 1
- 150000004706 metal oxides Chemical class 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000011973 solid acid Substances 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 230000007704 transition Effects 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
Landscapes
- Treatment Of Water By Ion Exchange (AREA)
- Hydroponics (AREA)
- Filtration Of Liquid (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】
〔発明の目的〕
、（産業上の利用分野）
本発明は原子力発電所の復水浄化設備に係り、とりわけ
−火水中の不純物除去を適切に制御することができる原
子力発電所の復水浄化設備に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Field of Application) The present invention relates to a condensate purification equipment for a nuclear power plant, and in particular - a nuclear power plant capable of appropriately controlling the removal of impurities in fire water. Concerning condensate purification equipment at power plants.
（従来の技術）
第７図に、従来の原子力発電所の概略系統図を示す。原
子炉圧力容器３１の一次水から発生した主蒸気はタービ
ン３２に導かれ、タービン３２を駆動した後、主復水器
３３にて凝縮され復水となる。この復水は低圧復水ポン
プ３４により、復水ろ過装置２および復水脱塩装置３か
らなる復水浄化設備１に移送される。(Prior Art) FIG. 7 shows a schematic system diagram of a conventional nuclear power plant. Main steam generated from primary water in the reactor pressure vessel 31 is guided to the turbine 32, drives the turbine 32, and is then condensed in the main condenser 33 to become condensed water. This condensate is transferred by a low-pressure condensate pump 34 to a condensate purification equipment 1 consisting of a condensate filtration device 2 and a condensate desalination device 3.
この復水浄化設備１でプラント構成材の腐蝕により発生
して復水中に混入するクラッド鉄（主として粒子状の金
属不純物）は除去される。In this condensate purification equipment 1, clad iron (mainly particulate metal impurities) generated due to corrosion of plant constituent materials and mixed into the condensate is removed.
ここでクラッドとは不溶解性固形分（全成分） ′をい
い、クラッド鉄とは不溶解性固形分のうち鉄分のみをい
う。Here, clad refers to the insoluble solid content (all components), and clad iron refers to only the iron content of the insoluble solid content.
この水は高圧復水ポンプ３７により給水加熱器３８に移
送されて加熱され、さらに給水ポンプ３９にて原子炉圧
力容器３１内へ給水され原子炉水４０となる。This water is transferred to the feed water heater 38 and heated by the high-pressure condensate pump 37, and further fed into the reactor pressure vessel 31 by the feed water pump 39 to become reactor water 40.
原子炉水４０の一部は、原子炉水浄化ポンプ４２により
原子炉水浄化ろ過脱塩装置４３に運ばれる。そしてこの
原子炉水浄化ろ過脱塩装置４３で原子炉水４０に含まれ
ているクラッド鉄が除去される。A portion of the reactor water 40 is conveyed to a reactor water purification filtration desalination device 43 by a reactor water purification pump 42 . Clad iron contained in the reactor water 40 is then removed by this reactor water purification filtration desalination device 43.
このようにして、プラント運転が安定して給水から送り
込まれるクラッド濃度が一定であれば、原子炉水４０の
クラッド濃度は、はぼ一定となる。In this way, if the plant operation is stable and the concentration of crud fed from the water supply is constant, the concentration of crud in the reactor water 40 will be approximately constant.
ところで、原子力発電所の放射線レベル上昇に寄与する
物質は、長半減期の放射性コバルトあるいは放射性ニッ
ケルであることが知られている。By the way, it is known that radioactive cobalt or radioactive nickel, which have long half-lives, are substances that contribute to an increase in radiation levels at nuclear power plants.
すなわち、これらの物質は、プラント構成材料の腐蝕に
より発生した非放射性コバルトあるいは非放射性ニッケ
ルが原子炉水４０中に混入し、これらが炉心部４１に運
ばれ中性子を浴びて放射性コバルトあるいは放射性ニッ
ケルとなったものであり、原子炉水４０の移動に伴って
拡散して原子力発電所の放射線レベルを上昇させる。ま
た、炉心部４１の構成材料に含まれる非放射性コバルト
あるいは非放射性ニッケルが中性子を浴びて放射性とな
り、これらが構成材料の腐蝕により原子炉水４０に混入
し拡散することも考えられる。In other words, these substances are non-radioactive cobalt or non-radioactive nickel generated due to corrosion of plant constituent materials mixed into the reactor water 40, transported to the reactor core 41, exposed to neutrons, and converted into radioactive cobalt or radioactive nickel. As the reactor water 40 moves, it spreads and increases the radiation level in the nuclear power plant. It is also conceivable that non-radioactive cobalt or non-radioactive nickel contained in the constituent materials of the reactor core 41 becomes radioactive when exposed to neutrons, and that these become mixed into the reactor water 40 and diffused due to corrosion of the constituent materials.
上記の放射性コバルトあるいは放射性ニッケルの拡散を
防ぐには、原子炉水４０のコバルト量あいろはニッケル
量の２倍程度のクラッド鉄を原子炉水４０に供給し、コ
バルトと鉄およびニッケルと鉄の金属酸化物（Ｃｏ Ｆ
ｅ ２０４ 。In order to prevent the above-mentioned diffusion of radioactive cobalt or radioactive nickel, clad iron is supplied to the reactor water 40 in an amount of cobalt or about twice the amount of nickel in the reactor water 40, and the metals of cobalt and iron and nickel and iron are Oxide (CoF
e204.
Ｎ ｔ ｐ ｅ ｔ） ｏ ４ ）として、炉心部４〕
の燃料表面に付着させ炉心部４１にとじこめておくこと
が必要である。N t p e t) o 4), the reactor core part 4]
It is necessary to attach the fuel to the surface of the fuel and confine it in the reactor core 41.
一方、原子炉水４０にクラッド鉄を持ち込み過ぎた場合
、コバルトと鉄およびニッケルと鉄の金属酸化物は燃料
表面に安定付着せずに燃料表面から原子炉水４０へ混入
し、炉心部４１より原子力発電設備内の各所へ拡散し、
プラント放射線レベルを上昇させることも知られている
。On the other hand, if too much clad iron is brought into the reactor water 40, the metal oxides of cobalt and iron and nickel and iron will not stably adhere to the fuel surface, but will mix into the reactor water 40 from the fuel surface, and from the reactor core 41. It spreads to various places within the nuclear power generation facility,
It is also known to increase plant radiation levels.
コバルトおよびニッケルの原子炉水４０への混入量は、
コバルトおよびニッケルを含むプラント構成材料の腐蝕
速度が経時的に変化するので、これに伴って経時的に変
化する。また、コバルトおよびニッケルを含むプラント
構成部品の消耗による部品交換によっても変化すること
となる。The amount of cobalt and nickel mixed into the reactor water 40 is
Corrosion rates of plant constituent materials containing cobalt and nickel change over time, and accordingly change over time. It will also change due to parts replacement due to wear and tear on plant components containing cobalt and nickel.
上述のように、原子炉水４０のクラッド鉄混入量は、原
子炉水４０へのコバルトおよびニッケルの混入量の２倍
程度にすることが必要なため、原子炉水４０へのコバル
トおよびニッケル変化に対応して原子炉水４０ヘクラツ
ド鉄を混入する必要がある。As mentioned above, the amount of clad iron mixed into the reactor water 40 needs to be about twice the amount of cobalt and nickel mixed into the reactor water 40, so the amount of cobalt and nickel mixed into the reactor water 40 is It is necessary to mix 40 hectares of iron into the reactor water correspondingly.
原子炉水４０へ混入するクラッド鉄の大半は、給水ポン
プ３９より原子炉圧力容器３１に送り込まれる給水中に
混入しているクラッド鉄である。Most of the clad iron mixed into the reactor water 40 is clad iron mixed into the water supply fed into the reactor pressure vessel 31 from the water supply pump 39.
この給水中のクラッド鉄の混入量を適切に制御するため
には、復水中に混入しているクラッド鉄を復水ろ過装置
２および復水脱塩装置３からなる復水浄化設備で除去し
て復水脱塩装置３の出口クラッド鉄濃度を適切に制御す
ることが求められている。In order to appropriately control the amount of clad iron mixed in this water supply, the clad iron mixed in the condensate must be removed by a condensate purification system consisting of a condensate filtration device 2 and a condensate desalination device 3. It is required to appropriately control the cladding iron concentration at the outlet of the condensate desalination device 3.
（発明が解決しようとする問題点）
しかしながら、この復水脱塩装置３の出口クラッド鉄濃
度の制御は、様々な問題がある。(Problems to be Solved by the Invention) However, there are various problems in controlling the outlet cladding iron concentration of the condensate desalination device 3.
すなわち、復水中のクラッド鉄の性状は以下のような変
化を示し、このため復水脱塩装置３の出口クラッド鉄濃
度の制御は困難となっている。That is, the properties of the clad iron in the condensate show the following changes, which makes it difficult to control the clad iron concentration at the outlet of the condensate desalination device 3.
（１） 復水中のクラッド鉄の性状は経時的に変化する
。従って、復水ろ過装置２が粉末樹脂圧カブリコート式
である場合、プリコート条件が同一であれば同じような
プリコート層を常に形成するので、これによるクラッド
鉄の除去性能が変化し復水ろ過装置２の出口クラッド鉄
濃度が変化する。(1) The properties of clad iron in condensate change over time. Therefore, if the condensate filtration device 2 is of the powder resin pressure fog coating type, a similar precoat layer will always be formed if the precoating conditions are the same, so the removal performance of clad iron will change due to this, and the condensate filtration device The outlet cladding iron concentration of 2 changes.
（２） 上記（１）の原因等によりまた復水脱塩装置の
クラッド鉄除去特性の劣化によって、復水脱塩装置３の
出口クラッド鉄濃度が変化する。(2) The cladding iron concentration at the outlet of the condensate desalination device 3 changes due to the causes mentioned in (1) above and due to deterioration of the cladding iron removal characteristics of the condensate desalination device.
（３） 前述のとおり、コバルトおよびニッケルの原子
炉への混入量は経時的に変化し、これにともない原子炉
への必要給水クラッド鉄濃度も経時的に変化する。(3) As mentioned above, the amount of cobalt and nickel mixed into the nuclear reactor changes over time, and accordingly, the concentration of cladding iron in the water required for the reactor also changes over time.
これらの変化のうち、一般的には変化（１）と変化（２
）は経時的に増加傾向、変化（３）は経時的に減少傾向
を示すので、必要給水クラッド鉄濃度に対する復水脱塩
装置３の出口クラッド鉄濃度制御は難しいと考えられて
いる。Among these changes, generally change (1) and change (2)
) shows an increasing trend over time, and change (3) shows a decreasing trend over time, so it is considered difficult to control the outlet clad iron concentration of the condensate desalination device 3 with respect to the required feed water clad iron concentration.
この場合、復水脱塩装置３のクラッド鉄の除去特性が、
復水ろ過装置２の出口クラッド鉄濃度によって変化する
ことを利用して、復水脱塩装置３の出口クラッド鉄濃度
を制御することができれば都合力５良い。In this case, the clad iron removal characteristics of the condensate desalination device 3 are
It would be advantageous if the cladding iron concentration at the outlet of the condensate desalination device 3 could be controlled by utilizing the fact that it changes depending on the cladding iron concentration at the outlet of the condensate filtration device 2.
本発明はこのような点を考慮してなされたものであり、
復水ろ過装置の出口クラッド鉄濃度を変化させ、このこ
とによって復水脱塩装置の出口クラッド鉄濃度を適切に
制御することができる原子力発電所の復水浄化設備を提
供することを目的とする。The present invention has been made in consideration of these points,
The purpose of the present invention is to provide condensate purification equipment for a nuclear power plant that can change the cladding iron concentration at the outlet of a condensate filtration device, thereby appropriately controlling the cladding iron concentration at the outlet of a condensate desalination device. .
（問題点を解決するための手段）
、本発明は、中空系膜フィルタが内装された復水ろ過器
を有する復水ろ過装置と、この復水ろ過装置に接続され
た復水脱塩装置とからなる原子力発電所の復水浄化設備
であって、前記復水ろ過装置に流量制御弁が取付けられ
たバイパスラインを設けたことを特徴としている。(Means for Solving the Problems) The present invention provides a condensate filtration device having a condensate filter equipped with a hollow membrane filter, and a condensate desalination device connected to this condensate filtration device. This is a condensate purification facility for a nuclear power plant, which is characterized in that the condensate filtration device is provided with a bypass line to which a flow rate control valve is attached.
（作 用）
本発明によれば、バイパスラインの流量制御弁によって
復水ろ過装置を通過させないバイパス流量を制御し、こ
のことによって復水ろ過装置出口のクラッド鉄濃度を制
御することができる。(Function) According to the present invention, the flow rate control valve of the bypass line controls the bypass flow rate that does not allow the condensate to pass through the condensate filtration device, thereby controlling the clad iron concentration at the outlet of the condensate filtration device.
（実施例） 以下図面を参照して本発明の実施例について説明する。(Example) Embodiments of the present invention will be described below with reference to the drawings.
第１図乃至第６図は本発明による原子力発電所の復水浄
化設備の一実施例を示す図である。第１図において、復
水浄化設備１は、人口弁７および出口弁８を有し中空系
膜フィルタを内装した復水ろ過器５を複数並列に配置し
てなる復水ろ過装置２と、この復水ろ過装置２の後方に
接続されるとともに人口弁１９および出口弁２０を有し
粒状のイオン交換樹脂を充てんした復水脱塩塔１８を複
数並列に配置してなる復水脱塩装置３とから構成されて
いる。1 to 6 are diagrams showing an embodiment of a condensate purification equipment for a nuclear power plant according to the present invention. In FIG. 1, the condensate purification equipment 1 includes a condensate filtration device 2 formed by arranging a plurality of condensate filters 5 in parallel, each having a population valve 7 and an outlet valve 8 and each containing a hollow membrane filter. A condensate desalination device 3 is connected to the rear of the condensate filtration device 2, and is formed by arranging in parallel a plurality of condensate desalination towers 18 each having a population valve 19 and an outlet valve 20 and filled with granular ion exchange resin. It is composed of.
また、各復水ろ過器５の人口弁７および出口弁８と、各
復水脱塩塔１８の人口弁１９および出口弁２０は自動制
御弁となっている。さらに復水ろ過器５と出口弁８との
間には、それぞれ復水ろ過器流量計６が設けられている
。Further, the artificial valve 7 and the outlet valve 8 of each condensate filter 5 and the artificial valve 19 and the outlet valve 20 of each condensate demineralizer 18 are automatic control valves. Further, a condensate filter flow meter 6 is provided between the condensate filter 5 and the outlet valve 8, respectively.
また、復水ろ過装置２には、大流量制御弁１１が取付ｌ
：ｌられた大流量バイパスライン１０と、小流量制御弁
１３が取付けられた小流量バイパスライン１２とが設け
られている。この小流量バイパスライン１２には小流量
バイパス流量計１４が設けられている。これらのバイパ
スラインのうち、小流量バイパスライン１２は２０％以
下のバイパス流量制御を行なうものであり、大流量バイ
パスライン１０は２０％以にのバイパス流量制御を行な
うものである。In addition, a large flow rate control valve 11 is attached to the condensate filtration device 2.
A large flow bypass line 10 is provided, and a small flow bypass line 12 is provided with a small flow control valve 13. This small flow bypass line 12 is provided with a small flow bypass flowmeter 14 . Among these bypass lines, the small flow bypass line 12 controls the bypass flow rate to 20% or less, and the large flow bypass line 10 controls the bypass flow rate to 20% or more.
また、各復水ろ過器５の復水ろ過器流量計６および小流
量バイパス流量計１４は流量演算器１５に接続され、こ
の流量演算器】５によって大流量制御弁１】および小流
；制御弁１３が制御される。Further, the condensate filter flow meter 6 and the small flow bypass flow meter 14 of each condensate filter 5 are connected to a flow rate calculator 15, and the large flow rate control valve 1] and the small flow are controlled by the flow rate calculator 5. Valve 13 is controlled.
またこの流量演算器１５には復水全流量信号が入力され
る。さらに流量演算８１５は流量表示器１６に接続され
、この流量表示器１６によって各復水ろ過器５の流量、
大流量バイパスライン１０および小流量バイパスライン
１２の流量が表示される。このうち大流量バイパスライ
ン１０の流量については、復水全流量、各復水ろ過器５
の流量および小流量バイパスライン１２の流量から求め
られる。Further, a condensate total flow rate signal is input to this flow rate calculator 15. Further, the flow rate calculation 815 is connected to the flow rate indicator 16, and the flow rate of each condensate filter 5 is determined by this flow rate indicator 16.
The flow rates of the large flow bypass line 10 and the small flow bypass line 12 are displayed. Among these, the flow rate of the large flow bypass line 10 is the total flow rate of condensate, each condensate filter 5
is determined from the flow rate of the flow rate and the flow rate of the small flow bypass line 12.
一方、復水脱塩装置３についても、制御弁２２が取付け
られた復水脱塩バイパスライン２１が設けられている。On the other hand, the condensate desalination device 3 is also provided with a condensate desalination bypass line 21 to which a control valve 22 is attached.
次にこのような構成からなる本実施例の作用について説
明する。Next, the operation of this embodiment having such a configuration will be explained.
まず復水ろ過装置２の出口クラッド鉄濃度の制御につい
て説明する。復水ろ過器５に内装されている中空系膜フ
ィルタのクラッド鉄除去特性は極めて良好であり、この
中空系膜フィルタで略１００％のクラッド鉄が除去され
ることが知られている６二のため、復水ろ過器５の出口
クラッド鉄濃度は略ゼロと考えることができる。First, control of the outlet clad iron concentration of the condensate filtration device 2 will be explained. The hollow membrane filter installed in the condensate filter 5 has extremely good cladding iron removal characteristics, and it is known that approximately 100% of cladding iron is removed by this hollow membrane filter. Therefore, the cladding iron concentration at the outlet of the condensate filter 5 can be considered to be approximately zero.
従って、復水ろ過装置２の出口クラッド鉄濃度は、復水
ろ過装置２の」二流側の復水クラッド鉄濃度とこの復水
ろ過装置２のバイパス流量によって定まる。一般にプラ
ント安定期では、復水クラッド濃度は略一定であるから
、復水ろ過装置２のバイパス流量によってかなり正確に
復水ろ過装置２の出口クラッド鉄濃度を制御することが
できる。Therefore, the outlet clad iron concentration of the condensate filtration device 2 is determined by the condensate clad iron concentration on the second-stream side of the condensate filtration device 2 and the bypass flow rate of the condensate filtration device 2. Generally, during the stable period of the plant, the condensate crud concentration is approximately constant, so the outlet crud iron concentration of the condensate filtration device 2 can be controlled fairly accurately by the bypass flow rate of the condensate filtration device 2.
例えば、復水ろ過装置２の上流側の復水クラ・ソド鉄濃
度が５ ｐｐｂであり復水ろ過装置２のバイパス流量が
２０％であれば、復水ろ過装置２の出口クラッド鉄濃度
は１ ｐｐｂとなる。また、バイパス流量が１０９６で
あれば復水ろ過装置２の出口クラッド鉄濃度はｏ、５ｐ
ｐｂ、バイパス流量が３０％であれば復水ろ過装置２の
出口クラッド鉄濃度は１、 ５ｐｐｂとなる。For example, if the condensate clad iron concentration on the upstream side of the condensate filtration device 2 is 5 ppb and the bypass flow rate of the condensate filtration device 2 is 20%, the outlet clad iron concentration of the condensate filtration device 2 is 1 ppb. Moreover, if the bypass flow rate is 1096, the outlet clad iron concentration of the condensate filtration device 2 is o, 5p
If the bypass flow rate is 30%, the clad iron concentration at the outlet of the condensate filtration device 2 will be 1.5 ppb.
次に大流量バイパスライン１０と小流量バイパスライン
１２の使用方法について説明する。Next, how to use the large flow bypass line 10 and the small flow bypass line 12 will be explained.
復水ろ過装置２の上流側の復水クラッド鉄濃度が略一定
（例えば、５ｐｐｂ）となっている場合、大流量バイパ
スライン１０の大流量制御弁１１の開度を略一定としバ
イパス流量を２０％とする。When the condensate clad iron concentration on the upstream side of the condensate filtration device 2 is approximately constant (for example, 5 ppb), the opening degree of the large flow rate control valve 11 of the large flow bypass line 10 is kept approximately constant, and the bypass flow rate is set to 20%. %.
そして、小流量バイパイライン１２の小流量制御弁１３
を用いて微調整することにより、復水ろ過装置２の出口
クラッド鉄濃度を略１ ｐｐｌ）に安定して制御するこ
とができる。The small flow control valve 13 of the small flow bypass line 12
By making fine adjustments using , it is possible to stably control the clad iron concentration at the outlet of the condensate filtration device 2 to approximately 1 ppl).
また、復水ろ過装置２の上流側の復水クラッド鉄濃度が
５ ｐｐｂ以上となった場合は、バイパス流量を２０％
以下とする。この場合は、大バイパスライン１０を閉と
し小バイパスライン１２のみを使用する。In addition, if the condensate clad iron concentration on the upstream side of the condensate filtration device 2 is 5 ppb or more, the bypass flow rate should be reduced by 20%.
The following shall apply. In this case, the large bypass line 10 is closed and only the small bypass line 12 is used.
このように復水ろ過装置２の出口クラッド鉄濃度を大流
量バイパスライン１０および小流量バイパスライン１２
を用いることによって、自動的に変化させることができ
る。In this way, the cladding iron concentration at the outlet of the condensate filtration device 2 is controlled by the large flow bypass line 10 and the small flow bypass line 12.
It can be changed automatically by using .
なお、この間の大バイパスライン１０および小バイパス
ライン１２を流れるバイパス流量と、各復水ろ過器５の
流量は流量表示器１６に表示される。また、バイパス流
量を確実に制御するために、大流量制御弁１１および小
流量制御弁１３による制御のみならず、例えば所定の復
水ろ過器５の入口弁７および出口弁８を閉としてバイパ
スｆｆ１ｆｆｌを増加させるよう制御することもできる
。Note that the bypass flow rate flowing through the large bypass line 10 and the small bypass line 12 during this time and the flow rate of each condensate filter 5 are displayed on the flow rate display 16. In order to reliably control the bypass flow rate, in addition to the control by the large flow rate control valve 11 and the small flow rate control valve 13, for example, the inlet valve 7 and outlet valve 8 of a predetermined condensate filter 5 are closed to bypass ff1ffl. It can also be controlled to increase.
続いて、復水ろ過装置２の出口クラッド鉄濃度を変化さ
せ、このことにより復水脱塩装置３の出口クラッド鉄濃
度を制御する。Subsequently, the outlet clad iron concentration of the condensate filtration device 2 is changed, thereby controlling the outlet clad iron concentration of the condensate desalination device 3.
以下、復水ろ過装置２の出口クラッド鉄濃度と復水脱塩
装置３の出口クラッド鉄濃度との関係を説明する。The relationship between the outlet clad iron concentration of the condensate filtration device 2 and the outlet clad iron concentration of the condensate desalination device 3 will be described below.
初めに、復水脱塩装置のクラッド鉄除去特性の概要を第
２図に示す。復水脱塩装置３は、粒径数百ミクロンのイ
オン交換樹脂１５を球形あるいは円筒形の復水脱塩器（
第１歯杆号１８）に充てんし、そのイオン交換樹脂１５
で充てん層内に復水を流すことにより、復水中の不純物
を除去するものである。復水中に含まれるクラッド鉄の
除去は、クラッド鉄とイオン交換樹脂２５の電気化学的
な正負の状態差の違いによりクラッド鉄がイオン交換樹
脂２５の表面に引き寄せられて付着する現象であること
が知られている。First, Figure 2 shows an overview of the crud iron removal characteristics of the condensate desalination equipment. The condensate demineralizer 3 is a spherical or cylindrical condensate demineralizer (
Fill the first tooth rod No. 18) with the ion exchange resin 15
Impurities in the condensate are removed by flowing the condensate into the packed layer. The removal of the clad iron contained in the condensate is a phenomenon in which the clad iron is attracted to and adheres to the surface of the ion exchange resin 25 due to the difference in electrochemical positive and negative states between the clad iron and the ion exchange resin 25. Are known.
従って、イオン交換樹脂２５の表面にクラッド鉄が付着
して、イオン交換樹脂２５の表面電位とクラッド鉄の電
位差が減少するとその除去率は低下する。反対に、イオ
ン交換樹脂２５の表面の付着鉄が少なくなれば、クラッ
ド鉄との電位差が増加してクラッド鉄の除去率は向上す
る。Therefore, when the clad iron adheres to the surface of the ion exchange resin 25 and the potential difference between the surface potential of the ion exchange resin 25 and the clad iron decreases, the removal rate decreases. On the contrary, if the amount of iron adhering to the surface of the ion exchange resin 25 decreases, the potential difference with the clad iron increases and the removal rate of the clad iron improves.
イオン交換樹脂２５のカチオン樹脂は固体酸であるから
、イオン交換樹脂２５表面上に付着したクラッド鉄は溶
解しイオン鉄２６となる。このイオン鉄２６は、樹脂内
の鉄濃度差により内部に拡散する。従って、ある速度で
イオン交換樹脂２５の表面上に付着したクラッド鉄は減
少する。これにより、イオン交換樹脂２５表面の電位が
変わりクラッド鉄を付着しやすくなる。Since the cation resin of the ion exchange resin 25 is a solid acid, the clad iron adhering to the surface of the ion exchange resin 25 is dissolved and becomes ionic iron 26. This ionic iron 26 diffuses into the resin due to the difference in iron concentration within the resin. Therefore, the clad iron deposited on the surface of the ion exchange resin 25 decreases at a certain rate. This changes the potential on the surface of the ion exchange resin 25, making it easier for clad iron to adhere.
以上より、復水脱塩装置３の出口クラッド鉄濃度が上昇
してイオン交換樹脂２５の付着鉄が増加方向であれば、
復水脱塩装置３のクラッド鉄除去率は低下し、復水脱塩
装置３の出口クラッド鉄濃度が低下して減少方向であれ
ば、復水脱塩装置３のクラッド鉄除去率は向上し、この
復水脱塩装置３の出口クラッド鉄濃度にはある境界が存
在するこの上記境界は、イオン交換樹脂２５のカチオン
樹脂量とアニオン樹脂量の体積比がｌ；１、イオン交換
樹脂２５の充てん層高が９０（７）、復水の線流速が１
２０ｍ／Ｈの復水脱塩装置において、イオン交換樹脂２
５の粒間鉄を除去した後の状態では、復水脱塩装置３の
出口クラッド鉄濃度が、約１ ｐｐｂであることが判明
した。From the above, if the outlet cladding iron concentration of the condensate desalination device 3 increases and the amount of iron adhering to the ion exchange resin 25 increases, then
The clad iron removal rate of the condensate desalination device 3 decreases, and if the outlet clad iron concentration of the condensate desalination device 3 decreases and is in the decreasing direction, the clad iron removal rate of the condensate desalination device 3 increases. , a certain boundary exists in the clad iron concentration at the outlet of the condensate desalination device 3. This boundary exists when the volume ratio of the cation resin amount to the anion resin amount of the ion exchange resin 25 is 1; Filled layer height is 90 (7), linear flow velocity of condensate is 1
In a 20 m/H condensate desalination equipment, ion exchange resin 2
It was found that the cladding iron concentration at the outlet of the condensate desalination device 3 was about 1 ppb in the state after removing the intergranular iron of No. 5.
このことにより、復水脱塩装置３の人口クラッド鉄濃度
、すなわち復水ろ過装置２の出口クラッド鉄濃度を上下
することによって、適切な範囲内に復水脱塩装置の出口
クラッド鉄濃度を制御することができる。As a result, by increasing and lowering the artificial clad iron concentration of the condensate desalination device 3, that is, the outlet clad iron concentration of the condensate filtration device 2, the outlet clad iron concentration of the condensate desalination device is controlled within an appropriate range. can do.
続いて第３図および第４図によって復水脱塩装置３のク
ラッド鉄除去特性および復水ろ過装置２のクラッド鉄除
去特性を利用したクラッド鉄濃度の制御について説明す
る。Next, control of the clad iron concentration using the clad iron removal characteristics of the condensate desalination device 3 and the clad iron removal characteristics of the condensate filtration device 2 will be explained with reference to FIGS. 3 and 4.
第３図のとおり、原子炉水のコバルトおよびニッケル混
入量に対応する（２倍をなす）必要給水クラッド鉄濃度
は原子力発電所の運転時間によっ。 て変化する。す
なわち、任意の運転時間に、必要給水クラッド鉄濃度が
存在する。As shown in Figure 3, the required feed water crud iron concentration corresponding to (double) the amount of cobalt and nickel mixed in reactor water depends on the operating hours of the nuclear power plant. and change. That is, at any given operating time, there is a required feedwater cladding iron concentration.
この必要給水クラッド鉄濃度に合せるよう復水ろ過装置
２のバイパス流量を大流量バイパスラインと小流量バイ
パスラインを用いて自動的に制御し、復水ろ過装置２の
出口クラッド鉄濃度を上下させ、これに伴って復水脱塩
装置３の出口クラッド鉄濃度を上下させて平均的に目標
給水クラッド鉄濃度を得ることができる。The bypass flow rate of the condensate filtration device 2 is automatically controlled using a large flow bypass line and a small flow bypass line to match this required water supply clad iron concentration, and the outlet clad iron concentration of the condensate filtration device 2 is increased or decreased. Along with this, the outlet cladding iron concentration of the condensate desalination device 3 is increased or decreased to obtain the target feed water cladding iron concentration on average.
すなわち、この目標クラッド鉄濃度を得るためには、第
４図に示すように、目標給水クラッド鉄濃度に対し、各
系統のクラッド鉄濃度の上限および下限を定めておく。That is, in order to obtain this target clad iron concentration, as shown in FIG. 4, the upper and lower limits of the clad iron concentration of each system are determined for the target clad iron concentration of the water supply.
そしてクラッド鉄濃度がこれら上限または下限のいずれ
かから外れた場合、復水ろ過器２のバイパス流量を変更
することによってクラッド鉄濃度を適正値に修正する。If the cladding iron concentration deviates from either the upper limit or the lower limit, the cladding iron concentration is corrected to an appropriate value by changing the bypass flow rate of the condensate filter 2.
この場合、経年的な復水のクラッド性状に対しても対応
できるようにバイパス流量を変更することにより、原子
力発電所のプラント寿命中の必要給水クラッド鉄濃度に
対する制御も行なうことができる。また、原子炉圧力容
器３１の炉心部４１に既に必要以上のクラッド鉄量が付
着している場合は、上記目標給水クラッド鉄濃度より低
目に制御しておき、原子炉水４０のニッケル及びコバル
トの放射能濃度を見て、上昇傾向を示した時に復水ろ過
装置２のバイパス流量を変更することもできる。In this case, by changing the bypass flow rate so as to be able to cope with the aging of condensate crud properties, it is also possible to control the required water supply crud iron concentration during the life of the nuclear power plant plant. In addition, if more crud iron than necessary is already attached to the reactor core 41 of the reactor pressure vessel 31, the concentration of crud iron in the reactor water 40 is controlled to be lower than the target crud iron concentration. It is also possible to change the bypass flow rate of the condensate filtration device 2 when the radioactivity concentration shows an upward trend.
また、原子力発電プラント運転開始初期は、コバルトお
よびニッケルの原子炉水４０への混入量が多く、必要給
水クラッド鉄濃度が高くなり、復水脱塩装置３のイオン
交換樹脂２５が極めて清浄でクラッド鉄除去性能が良い
ことが知られている。In addition, at the beginning of operation of a nuclear power plant, the amount of cobalt and nickel mixed into the reactor water 40 is large, and the required water supply water cladding iron concentration becomes high, and the ion exchange resin 25 of the condensate desalination equipment 3 is extremely clean and the cladding It is known to have good iron removal performance.
従って、このような時期には早期に復水脱塩装置３のイ
オン交換樹脂２５を汚して除去性能を下げる必要がある
。このため、復水ろ過装置２の大バイパスライン１０の
大流量制御弁１１の開度を大とし、バイパス流量を多く
する。さらにバイパス流量を増加するためには、復水ろ
過器５の入口弁７と復水ろ過器５の出口弁８を閉とする
。必要に応じ、閉とする入口弁７および出口弁８の個数
を増加すれば、バイパス流量は増加することとなる。Therefore, in such a period, it is necessary to quickly pollute the ion exchange resin 25 of the condensate desalination device 3 to lower the removal performance. For this reason, the opening degree of the large flow rate control valve 11 of the large bypass line 10 of the condensate filtration device 2 is increased to increase the bypass flow rate. In order to further increase the bypass flow rate, the inlet valve 7 of the condensate filter 5 and the outlet valve 8 of the condensate filter 5 are closed. By increasing the number of inlet valves 7 and outlet valves 8 that are closed as necessary, the bypass flow rate will increase.
続いて第５図に、復水ろ過器２のバイパス流量を変化さ
せた場合のクラッド鉄濃度変化の実績を示す。Next, FIG. 5 shows the results of changes in cladding iron concentration when the bypass flow rate of the condensate filter 2 was changed.
このように本実施例によれば、復水ろ過装置２のバイパ
ス流量を変化させることによって、原子炉水に混入した
コバルトおよびニッケルの量に対応する必要クラッド鉄
量を適切に原子炉水に混入することができる。In this way, according to this embodiment, by changing the bypass flow rate of the condensate filtration device 2, the necessary amount of cladding iron corresponding to the amount of cobalt and nickel mixed into the reactor water can be appropriately mixed into the reactor water. can do.
第８図に示すように、原子炉水へのクラッド鉄混入量が
必要クラッド鉄量より多くても少なくても、従業者への
被曝線量は増加する。従って、必要クラッド鉄量を適切
に原子炉水に混入することによって、この従業者への被
曝線量を容易に減少させることができる。As shown in FIG. 8, whether the amount of clad iron mixed into the reactor water is greater or less than the required amount of clad iron, the radiation dose to workers increases. Therefore, by appropriately mixing the necessary amount of cladding iron into reactor water, the radiation dose to these workers can be easily reduced.
また、本実施例によれば、大流量のバイパス流量につい
ては大流量バイパスラインを、小流量のバイパス流量に
ついては小流量バイパスラインをそれぞれ用いることが
できるので、流量の大小に応じた適切なバイパス流量制
御を行なうことができる。Furthermore, according to this embodiment, the large-flow bypass line can be used for a large bypass flow rate, and the small-flow bypass line can be used for a small bypass flow rate. Flow rate control can be performed.
本発明によれば、復水ろ過装置のバイパス流量を制御し
て復水ろ過装置の出口クラッド鉄濃度を制御することに
より、原子炉へ必要クラッド鉄量を適切に混入すること
ができる。このため従業者に対する被曝線量を低下させ
て、安全な原子力発電所を提供することができる。According to the present invention, by controlling the bypass flow rate of the condensate filtration device and controlling the cladding iron concentration at the outlet of the condensate filtration device, it is possible to appropriately mix the required amount of cladding iron into the nuclear reactor. Therefore, it is possible to reduce the radiation dose to workers and provide a safe nuclear power plant.
第１図は本発明による原子力発電所の復水浄化設備の一
実施例を示す概略系統図、第２図は復水脱塩装置におけ
るクラッド鉄の除去率フローおよび移行フローを示す図
、第３図は原子力発電所のプラント運転時間に対する必
要給水クラッド鉄濃度を示す図、第４図は各系統のクラ
ッド鉄濃度を示す図、第５図は所定のバイパス流量を定
めた場合の各系統のクラッド鉄濃度の実績値を示す図、
第６図は原子炉のクラッド鉄混入量に対するプラント定
検時の従業者被曝線量を示す図、第７図は従来の原子力
発電所の概略系統図である。
１・・・復水浄化設備、２・・・復水ろ過装置、３・・
・復水脱塩装置、５・・・復水ろ過器、７・・・入口弁
、８・・・出口弁、１０・・・大流量バイパスライン、
１１・・・大流量制御弁、１２・・・小流量バイパスラ
イン、１３・・・小流量制御弁。FIG. 1 is a schematic system diagram showing an embodiment of the condensate purification equipment for a nuclear power plant according to the present invention, FIG. 2 is a diagram showing the removal rate flow and transition flow of clad iron in the condensate desalination equipment, and FIG. The figure shows the required water supply cladding iron concentration for nuclear power plant operating hours, Figure 4 shows the cladding iron concentration in each system, and Figure 5 shows the cladding iron concentration in each system when a predetermined bypass flow rate is determined. Diagram showing actual values of iron concentration,
FIG. 6 is a diagram showing the radiation exposure dose of workers during regular plant inspections with respect to the amount of crud iron mixed in the reactor, and FIG. 7 is a schematic diagram of a conventional nuclear power plant. 1... Condensate purification equipment, 2... Condensate filtration device, 3...
・Condensate desalination device, 5... Condensate filter, 7... Inlet valve, 8... Outlet valve, 10... Large flow bypass line,
11... Large flow control valve, 12... Small flow bypass line, 13... Small flow control valve.
Claims (1)
復水ろ過装置と、この復水ろ過装置に接続された復水脱
塩装置とからなる原子力発電所の復水浄化設備において
、前記復水ろ過装置に流量制御弁が取付けられたバイパ
スラインを設けたことを特徴とする原子力発電所の復水
浄化設備。 ２、バイパスラインは、小流量のバイパス流量を制御す
る小流量バイパスラインと、大流量のバイパス流量を制
御する大流量バイパスラインとによって構成されている
ことを特徴とする特許請求の範囲第１項に記載の原子力
発電所の復水浄化設備。[Claims] 1. A nuclear power plant recovery system consisting of a condensate filtration device having a condensate filter equipped with a hollow membrane filter, and a condensate desalination device connected to this condensate filtration device. A condensate purification facility for a nuclear power plant, characterized in that the condensate filtration device is provided with a bypass line to which a flow rate control valve is attached. 2. Claim 1, characterized in that the bypass line is composed of a small flow bypass line that controls a small bypass flow rate and a large flow bypass line that controls a large bypass flow rate. Condensate purification equipment for nuclear power plants as described in .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62093646A JPH0769460B2 (en) | 1987-04-16 | 1987-04-16 | Condensate purification equipment at a nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62093646A JPH0769460B2 (en) | 1987-04-16 | 1987-04-16 | Condensate purification equipment at a nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63259498A true JPS63259498A (en) | 1988-10-26 |
| JPH0769460B2 JPH0769460B2 (en) | 1995-07-31 |
Family
ID=14088133
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62093646A Expired - Lifetime JPH0769460B2 (en) | 1987-04-16 | 1987-04-16 | Condensate purification equipment at a nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0769460B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN117566979A (en) * | 2024-01-16 | 2024-02-20 | 深圳市汉斯顿净水设备有限公司 | Multi-flux self-adjusting filtering type water purifier and control method thereof |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61245093A (en) * | 1985-04-23 | 1986-10-31 | 株式会社日立製作所 | Feedwater system of nuclear power generating plant |
-
1987
- 1987-04-16 JP JP62093646A patent/JPH0769460B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61245093A (en) * | 1985-04-23 | 1986-10-31 | 株式会社日立製作所 | Feedwater system of nuclear power generating plant |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN117566979A (en) * | 2024-01-16 | 2024-02-20 | 深圳市汉斯顿净水设备有限公司 | Multi-flux self-adjusting filtering type water purifier and control method thereof |
| CN117566979B (en) * | 2024-01-16 | 2024-03-22 | 深圳市汉斯顿净水设备有限公司 | Multi-flux self-adjusting filtering type water purifier and control method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0769460B2 (en) | 1995-07-31 |
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