JPH0198998A - Controller for water quality of condensate/feed water system of reactor - Google Patents
Controller for water quality of condensate/feed water system of reactorInfo
- Publication number
- JPH0198998A JPH0198998A JP62254752A JP25475287A JPH0198998A JP H0198998 A JPH0198998 A JP H0198998A JP 62254752 A JP62254752 A JP 62254752A JP 25475287 A JP25475287 A JP 25475287A JP H0198998 A JPH0198998 A JP H0198998A
- Authority
- JP
- Japan
- Prior art keywords
- water
- reactor
- crud
- condensate
- water supply
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 135
- 238000005253 cladding Methods 0.000 claims description 30
- 238000003908 quality control method Methods 0.000 claims description 16
- 239000012510 hollow fiber Substances 0.000 claims description 5
- 239000012528 membrane Substances 0.000 claims description 4
- 238000011144 upstream manufacturing Methods 0.000 claims 1
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 abstract description 42
- 229910052742 iron Inorganic materials 0.000 abstract description 11
- 238000007689 inspection Methods 0.000 abstract description 7
- 230000005855 radiation Effects 0.000 abstract description 2
- 238000009825 accumulation Methods 0.000 abstract 2
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 230000003134 recirculating effect Effects 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 6
- 238000011084 recovery Methods 0.000 description 4
- 229910001030 Iron–nickel alloy Inorganic materials 0.000 description 3
- 238000001179 sorption measurement Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 229910002518 CoFe2O4 Inorganic materials 0.000 description 1
- 229910000990 Ni alloy Inorganic materials 0.000 description 1
- 238000011001 backwashing Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000007257 malfunction Effects 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 239000002699 waste material 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
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
この発明は、原子炉復・給水系の水質制御装置に係り、
特に給水のＦｅ１度を最適に制御することによって炉水
中のイオン放射能濃度を低減させる原子炉復・給水系の
水質制御装置に関する。[Detailed description of the invention] [Objective of the invention] (Industrial application field) This invention relates to a water quality control device for a nuclear reactor condensation/water supply system,
In particular, the present invention relates to a water quality control device for a reactor reactor water supply system that reduces the concentration of ion radioactivity in reactor water by optimally controlling the Fe1 degree of the feed water.
（従来の技術）
沸騰水型原子炉（ＢＷＲ）が適用された原子力発電プラ
ントでは、原子炉からの蒸気はタービンに供給され、こ
のタービンで仕事をした後復水器内で復水となる。この
復水は復水ろ過器および復水脱塩器によって順次浄化さ
れた後、給水加熱器で加熱され、原子犯に導かれる。(Prior Art) In a nuclear power plant to which a boiling water reactor (BWR) is applied, steam from the nuclear reactor is supplied to a turbine, performs work in the turbine, and then becomes condensed in a condenser. This condensate is sequentially purified by a condensate filter and a condensate demineralizer, then heated by a feed water heater and led to the atomic bomb.
このように、従来の原子炉復・給水系においては、復水
ろ過器および復水脱塩器により、給水から鉄を主成分と
するクラッドが除去される。そして、従来は、給水中の
クラッドか少ないほど放射能が少なくなるとの観点から
、給水中のクラッドをできる限り少なくするよう考慮さ
れていた。As described above, in the conventional nuclear reactor condensate/feedwater system, crud containing iron as a main component is removed from the feedwater by the condensate filter and the condensate demineralizer. Conventionally, from the viewpoint that the less crud in the water supply, the less radioactivity there is, consideration has been given to reducing the amount of crud in the water supply as much as possible.
（発明が解決しようとする問題点）
しかしながら、Ｎｉ合金製配管が多用された近年の原子
力発電プラントでは、給水中のクラッドを極端に減少さ
せると、鉄によるイオン放射能（６０ＣＯ２＋）の吸着
除去効果等が低下して、炉水中のイオン放射能濃度が上
昇してしまう。その結束、原子炉内または再循環系統内
等にイオン放射能が蓄積し、原子炉等の点検作業時に、
作業員が被曝するおそれがある。そして、この被曝を回
避するために、メンテナンスコストが上昇してしまう。(Problem to be solved by the invention) However, in recent nuclear power plants where Ni alloy piping is frequently used, if the amount of crud in the water supply is extremely reduced, the effect of adsorption and removal of ionic radioactivity (60CO2+) by iron is etc., and the concentration of ion radioactivity in the reactor water increases. Ion radioactivity accumulates in the bundle, inside the reactor or in the recirculation system, etc., and during inspection work on the reactor, etc.
Workers may be exposed to radiation. In order to avoid this exposure, maintenance costs increase.
この発明は、上記事実を考慮してなされたものであり、
原子炉内等におけるイオン放射能の蓄積量を減少させて
、原子炉等の点検作業時における作業員の被曝を低減す
ることができる原子炉復・−給水系の水質制御装置を提
供することを目的とする。This invention was made in consideration of the above facts,
It is an object of the present invention to provide a water quality control device for a reactor recovery/water supply system that can reduce the amount of ion radioactivity accumulated in a nuclear reactor, etc., and reduce the exposure of workers during inspection work of a nuclear reactor, etc. purpose.
（問題点を解決するための手段）
この発明は、原子力発電プラントの復水ろ過器に中空糸
膜フィルタが適用された原子炉復・給水系の給水の水質
を制御づる原子炉復・給水系の水質制御装置において、
上記復水ろ過器の逆洗水受タンクに連結されて逆洗水中
に含まれるクラッドを貯蔵するクラッド貯蔵タンクと、
高圧給水ポンプの下流側に設けられて給水中の［ｅ−Ｎ
ｉ比を検出する水質検出器と、この検出器に接続されＦ
ｅ−Ｎｉ比が所定値以下になったときに」−記クラッド
貯蔵タンク中のクラッドを給水中に混入さゼるコントロ
ーラとを有して構成されたものである。(Means for Solving the Problems) This invention provides a reactor condensate/feed water system for controlling the water quality of the feed water in the reactor condensate/feed water system in which a hollow fiber membrane filter is applied to the condensate filter of a nuclear power plant. In water quality control equipment,
a crud storage tank connected to the backwash water receiving tank of the condensate filter to store crud contained in the backwash water;
[e-N] installed downstream of the high-pressure water supply pump and
A water quality detector that detects the i ratio, and a water quality detector connected to this detector.
The controller is configured to mix the cladding in the cladding storage tank into the water supply when the e-Ni ratio falls below a predetermined value.
（作用）
したがって、この発明に係る原子炉復・給水系の水質制
御装置は、逆洗水受タンクに含まれるクラッドを原子炉
へ供給される給水中に混入させることにより、Ｆｅ−Ｎ
ｉ比を所定値以上に維持して鉄によるイオン放射能の吸
着効果を促進させ、炉水中のイオン放射能濃度を低減さ
せるものである。(Function) Therefore, the water quality control device for a reactor condensing/feeding system according to the present invention has Fe-N
The i ratio is maintained at a predetermined value or higher to promote the adsorption effect of ion radioactivity by iron, thereby reducing the ion radioactivity concentration in reactor water.
（実施例） 以下、この発明の実施例を図面に基づいて説明する。(Example) Embodiments of the present invention will be described below based on the drawings.
第１図はこの発明に係る原子炉復・給水系の水質制御装
置が適用された原子炉復・給水系を示す系統図である。FIG. 1 is a system diagram showing a reactor converter/water supply system to which a water quality control device for a reactor converter/supply system according to the present invention is applied.
原子炉１で発生した蒸気は、高圧タービン３および低圧
タービン５へ順次供給され、これらのタービン３，５で
仕事をする。その後、蒸気は、復水器７で復水となる。Steam generated in the nuclear reactor 1 is sequentially supplied to a high pressure turbine 3 and a low pressure turbine 5, and these turbines 3 and 5 perform work. Thereafter, the steam becomes condensed water in the condenser 7.
復水は、復水ポンプ９によって、復水ろ過器１１および
復水脱塩器１３へ順次供給されて浄化される。浄化され
た復水は、低圧給水ポンプ１５へ導かれて給水となり、
給水加熱器１７で加熱された後高圧給水ポンプ１９へ導
かれる。給水は、高圧給水ポンプ１９で昇圧されて原子
炉１へ供給される。The condensate is sequentially supplied to a condensate filter 11 and a condensate demineralizer 13 by a condensate pump 9 and purified. The purified condensate is led to the low-pressure water supply pump 15 and becomes water supply,
After being heated by the feed water heater 17, it is led to the high pressure feed water pump 19. The feed water is pressurized by a high-pressure feed water pump 19 and supplied to the reactor 1 .
上記復水ろ過器１１は、中空糸膜フィルタをろ過装置と
して採用したものである。この復水ろ過器により、復水
中の鉄を主成分とするクラッドが好適に除去され、復水
はほとんど純水に近い状態となる。また、復水ろ過器１
１には逆洗水受タンク２１が接続され、復水ろ過器１１
の逆洗後の逆洗水が貯留される。この逆洗水中には多用
のクラッドが含まれる。したがって、逆洗水受タンク２
１に貯留された逆洗水の殆どは、廃液処理系に導かれて
処理される。The condensate filter 11 employs a hollow fiber membrane filter as a filtration device. With this condensate filter, crud containing iron as a main component in the condensate is suitably removed, and the condensate becomes almost pure water. In addition, condensate filter 1
A backwash water receiving tank 21 is connected to the condensate filter 11.
Backwash water after backwashing is stored. This backwash water contains a lot of crud. Therefore, backwash water receiving tank 2
Most of the backwash water stored in 1 is led to the waste liquid treatment system and treated.
上述のような原子炉復・給水系に水質制御装置２３が設
置される。この水質制御装置２３はクラッド貯蔵タンク
２５、クラッド導入系２７、水質検出器２９およびコン
トローラ３１を有して構成される。A water quality control device 23 is installed in the reactor recovery/water supply system as described above. This water quality control device 23 includes a cladding storage tank 25, a cladding introduction system 27, a water quality detector 29, and a controller 31.
クラッド貯蔵タンク２５は、逆洗水受タンク２１に連結
されて、逆洗水中に含まれるクラッドを貯蔵する。また
、クラッド導入系２７はタラッド貯蔵タンク２５に連結
され、他端が低圧給水ポンプ１５および給水加熱器１７
間の給水配管に接続される。このクラッド導入系２７に
は、クラッド貯蔵タンク２５の側から順次クラッド供給
ポンプ３３およびクラッド供給弁３５が配設されて、ク
ラッド貯蔵タンク２５中のクラッドを給水中に混入可能
とする。The crud storage tank 25 is connected to the backwash water receiving tank 21 and stores crud contained in the backwash water. Further, the cladding introduction system 27 is connected to the cladding storage tank 25, and the other end is connected to the low pressure feed water pump 15 and the feed water heater 17.
Connected to the water supply piping between the two. A cladding supply pump 33 and a cladding supply valve 35 are arranged in this cladding introduction system 27 in order from the cladding storage tank 25 side, so that the cladding in the cladding storage tank 25 can be mixed into the water supply.
水質検出器２９は、原子炉復・給水系の高圧給水ポンプ
１９の下流側に設けられる。またこの水質検出器２９は
、濁度計３７、イオンクロマト計３８および処理部３９
から構成される。濁度計３７は、原子炉１へ供給される
給水中のクラッド濃度を測定し、このクラッド濃度から
Ｆｅ）１１１度を検出する。イオンクロマト計３８は、
原子炉１へ供給される給水中のＮｉ濃度を検出する。処
理部３９は、濁度計３７およびイオンクロマト計３８か
らのＦｃＪＩ度およびＮｉ濃度からＦｅ−Ｎｉ比（Ｆｅ
／Ｎ ｉ ）を算出し、その算出値をコントローラ３１
へ出力する。The water quality detector 29 is provided on the downstream side of the high-pressure water supply pump 19 of the reactor recovery/water supply system. Additionally, this water quality detector 29 includes a turbidity meter 37, an ion chromatometer 38, and a processing section 39.
It consists of The turbidity meter 37 measures the crud concentration in the feed water supplied to the reactor 1, and detects Fe) 111 degrees from this crud concentration. The ion chromatometer 38 is
The Ni concentration in the feed water supplied to the reactor 1 is detected. The processing unit 39 calculates the Fe-Ni ratio (Fe
/N i ), and the calculated value is sent to the controller 31.
Output to.
コントローラ３１は、水質検出器２つの処理部３９に電
気的に接続されるとともに、クラッド導入系２７のクラ
ッド供給ポンプ３３およびクラッド供給弁３５にも同様
に接続される。そして、このコントローラ３１は、処理
部３９にて算出されたＦｅ／Ｎｉが所定値（例えば約５
゜この値はプラント運転歴によって変わる。）以下のと
きに、クラッド供給弁３５へ開信号を出力し、クラッド
供給ポンプ３３へ起動信号を出力して、クラッド貯蔵タ
ンク２５中のクラッドを給水中に混入させるよう設けら
れる。また、この場合、クラッドは一点鎖線で示すよう
に、給水を経ずに直接原子炉１に供給されても良い。ク
ラッド供給弁３５の弁開度は、処理部３９にて算出され
たＦｅ／Ｎｉの値とＦｅ／Ｎｉの所定値との差に基づい
て調整される。The controller 31 is electrically connected to the processing units 39 of the two water quality detectors, and is similarly connected to the cladding supply pump 33 and cladding supply valve 35 of the cladding introduction system 27 . Then, this controller 31 determines that the Fe/Ni calculated by the processing unit 39 is a predetermined value (for example, about 5
゜This value varies depending on the plant operating history. ) At the following times, an open signal is output to the cladding supply valve 35, a start signal is outputted to the cladding supply pump 33, and the cladding in the cladding storage tank 25 is mixed into the water supply. Moreover, in this case, the cladding may be directly supplied to the nuclear reactor 1 without passing through the water supply, as shown by the dashed line. The opening degree of the cladding supply valve 35 is adjusted based on the difference between the Fe/Ni value calculated by the processing section 39 and a predetermined Fe/Ni value.
上述のようにＦｅ／Ｎｉを所定値以上に維持するのは次
の理由による。給水中のＦｅ／Ｎｉと炉水中のイオン放
射能（６０ＣＯ”＞ １５度との関係は、例えば運転初
期には第２図に示すように、Ｆｅ／Ｎｉが約５よりも低
い領域では炉水中のイオン族射性濃痕が高いが、給水中
のＦｅ／Ｎｉが約５以上のときは炉水中のイオン放射性
濃度が著しく低くなる。そこで、給水中のＦｅ／Ｎｉを
約５以上に維持して、炉水中のイオン放射性濃度を低く
抑えるためである。The reason why Fe/Ni is maintained above a predetermined value as described above is as follows. The relationship between Fe/Ni in the feed water and ion radioactivity in the reactor water (60CO"> 15 degrees is, for example, as shown in Figure 2 at the beginning of operation. Although the ion radioactivity concentration in the reactor water is high, when Fe/Ni in the feed water is about 5 or more, the ion radioactivity concentration in the reactor water becomes extremely low.Therefore, the Fe/Ni in the feed water is maintained at about 5 or more. This is to keep the ion radioactivity concentration in the reactor water low.
次に、作用効果を説明する。Next, the effects will be explained.
原子炉１へ供給される給水のＦｅ／Ｎｉが水質検出器２
９によって所定値以下であると検出されたときに、コン
トローラ３１はクラッド導入系２７を介して、クラッド
貯蔵タンク２５からのクラッドを給水中へ混入する。こ
れにより給水中のＦｅ濃度が上昇し、給水中のＦｅ／Ｎ
ｉを所定値以上に維持することができる。The water quality detector 2 detects Fe/Ni in the feed water supplied to the reactor 1.
9, the controller 31 mixes crud from the crud storage tank 25 into the water supply via the crud introduction system 27. As a result, the Fe concentration in the water supply increases, and Fe/N in the water supply increases.
i can be maintained at a predetermined value or higher.
給水中のＦｅ／Ｎｉを所定値以上にすることによって、
炉水中において、
・２＋
Ｎ ＋ ＋Ｆｅ２Ｏ３＋Ｈ２０
→ Ｎ １Ｆｅ２０４＋２Ｈ＋ ・−−−−−■
６０Ｃ０２＋十Ｆｅ２Ｏ３＋Ｈ２０
→ ＣｏＦｅ２Ｏ４＋２Ｈ・・・・−■で示される反
応が進行する。これらの式■、■で示されるように、炉
水中でイオン放射能（６０ＣＯ２”）が鉄により吸着除
去されるため、炉水中のイオン放射能濃度が低減される
。その結果、原子炉内および再循環系統内におけるイオ
ン放射能の蓄積量を減少することができ、原子炉等の点
検作業時における作業員の被曝を低減することができる
。By increasing Fe/Ni in the water supply to a predetermined value or higher,
In reactor water, ・2+ N + +Fe2O3+H20 → N 1Fe204+2H+ ・−−−−−■
60C02+10Fe2O3+H20 → CoFe2O4+2H...--The reaction proceeds. As shown by these equations ■ and ■, the ionic radioactivity (60CO2") in the reactor water is adsorbed and removed by iron, so the ionic radioactivity concentration in the reactor water is reduced. As a result, the concentration of ionic radioactivity in the reactor water is reduced. It is possible to reduce the amount of ion radioactivity accumulated in the recirculation system, and it is possible to reduce the radiation exposure of workers during inspection work of nuclear reactors and the like.
また、原子炉復・給水系に新たに鉄を注入するのではな
く、逆洗水受タンク２１からのクラッドを利用し、クラ
ッド注入を閉じた系で行なうことから、原子力発電プラ
ント全体のクラッド総量を増加させることな（、給水中
の鉄濃度を制御することができる。さらに、系統外から
鉄を注入しないので、この注入した鉄が給水加熱器等へ
付着するおそれも少ない。In addition, since the crud from the backwash water receiving tank 21 is used instead of newly injecting iron into the reactor water supply system and the crud is injected in a closed system, the total amount of crud in the entire nuclear power plant is reduced. It is possible to control the iron concentration in the water supply without increasing the iron concentration.Furthermore, since iron is not injected from outside the system, there is less risk of the injected iron adhering to the water supply heater, etc.
また、中空糸膜フィルタから構成される復水ろ過器で浄
化されてほぼ純水に近い状態となった給水にクラッドを
混入するので、給水中のＦｅ１５度つまりＦｅ／Ｎｉの
制御を極めて容易に行なうことができる。In addition, since cladding is mixed into the water supply that has been purified by a condensate filter consisting of a hollow fiber membrane filter and has become almost pure water, it is extremely easy to control Fe15 degrees, or Fe/Ni, in the water supply. can be done.
なお、上記実施例では、クラッド注入系２７の他端が、
原子炉復・給水系の低圧給水ポンプ１５および給水加熱
器１７間に接続されたものにつき説明したが、このクラ
ッド導入系２７の他端を給水加熱器１７および高圧給水
ポンプ１９間に接続させてもよい。この他の実施例の場
合には、前記実施例の効果に比べ、給水加熱器１７内に
ほぼ純水状態の給水を流すことになるので、給水加熱器
１７の故障等を低減でき、保守点検を容易化できる。In addition, in the above embodiment, the other end of the cladding injection system 27 is
Although the explanation has been given on the one connected between the low-pressure feedwater pump 15 and the feedwater heater 17 of the reactor recovery/feedwater system, the other end of this cladding introduction system 27 is connected between the feedwater heater 17 and the high-pressure feedwater pump 19. Good too. In the case of this other embodiment, compared to the effects of the above-mentioned embodiments, since almost pure water is allowed to flow into the feed water heater 17, malfunctions of the feed water heater 17 can be reduced, and maintenance and inspections can be reduced. can be facilitated.
以上のように、この発明に係る原子炉復・給水系の水質
制御装置によれば、中空糸ｎＱフィルタを用いた復水ろ
過器の逆洗水受タンクに連結され、逆洗水中に含まれる
クラッドを貯蔵するクラッド貯蔵タンクと、高圧給水ポ
ンプの下流側に設けられて給水中のＦｅ−Ｎｉ比を検出
する水質検出器と、この検出器に接続され、Ｆｅ−Ｎｉ
比が所定値以下になったときにクラッド貯蔵タンク中の
クラッドを給水中に混入させるコントローラとを有して
構成されることから、逆洗水受タンクから混入されるク
ラッドにより給水中のＦｅ−Ｎｉ比を所定値以上に維持
して、Ｆｅによるイオン放射能の吸着除去効果を促進さ
せ、炉水中のイオン放射能濃度を低減することができる
。その結果、原子炉内におけるイオン放射能の蓄積量を
減少させることができ、原子炉等の点検作業時における
作業員の被曝を低減することができる。As described above, according to the water quality control device for a nuclear reactor condensate/feed water system according to the present invention, the water quality control device is connected to the backwash water receiving tank of the condensate filter using the hollow fiber nQ filter, and the water contained in the backwash water is A cladding storage tank for storing cladding, a water quality detector installed downstream of the high-pressure water supply pump to detect the Fe-Ni ratio in the water supply, and a water quality detector connected to this detector to detect the Fe-Ni ratio in the water supply.
Since the controller includes a controller that mixes crud in the crud storage tank into the water supply when the ratio falls below a predetermined value, the crud mixed in from the backwash water receiving tank reduces Fe- By maintaining the Ni ratio above a predetermined value, the effect of adsorption and removal of ion radioactivity by Fe can be promoted, and the concentration of ion radioactivity in reactor water can be reduced. As a result, the amount of ion radioactivity accumulated in the reactor can be reduced, and the radiation exposure of workers during inspection work of the reactor etc. can be reduced.
第１図はこの発明に係る原子炉復・給水系の水質制御装
置が適用された原子炉復・給水系を示す系統図、第２図
は給水中のＦｅ／Ｎｉと炉水中のイオン放射能濃度との
関係を示すグラフである。
１・・・原子炉、３・・・高圧タービン、５・・・低圧
タービン、７・・・復水器、１１・・・復水ろ過器、１
７・・・給水加熱器、１９・・・高圧給水ポンプ、２１
・・・逆洗水受タンク、２３・・・水質制御装置、２５
・・・クラッド貯蔵タンク、２７・・・クラッド導入系
、２９・・・水質検出器、３１・・・コントローラ。
５笑乎Ｃマ←き橿撮榴悟便Fig. 1 is a system diagram showing a reactor converter/water supply system to which the reactor converter/supply water quality control device according to the present invention is applied, and Fig. 2 shows Fe/Ni in the feed water and ion radioactivity in the reactor water. It is a graph showing the relationship with concentration. 1... Nuclear reactor, 3... High pressure turbine, 5... Low pressure turbine, 7... Condenser, 11... Condensate filter, 1
7... Feed water heater, 19... High pressure water pump, 21
...Backwash water receiving tank, 23...Water quality control device, 25
... cladding storage tank, 27... cladding introduction system, 29... water quality detector, 31... controller. 5 Laughter C Ma
Claims (1)
タが適用された原子炉復・給水系の給水の水質を制御す
る原子炉復・給水系の水質制御装置において、上記復水
ろ過器の逆洗水受タンクに連結されて逆洗水中に含まれ
るクラッドを貯蔵するクラッド貯蔵タンクと、高圧給水
ポンプの下流側に設けられて給水中のＦｅ・Ｎｉ比を検
出する水質検出器と、この検出器に接続され、Ｆｅ・Ｎ
ｉ比が所定値以下になつたときに上記クラッド貯蔵タン
ク中のクラッドを給水中に混入させるコントローラとを
有することを特徴とする原子炉復・給水系の水質制御装
置。 ２、コントローラは、クラッド貯蔵タンク中のクラッド
を、給水加熱器の上流側の給水中に混入させる特許請求
の範囲第１項記載の原子炉復・給水系の水質制御装置。 ３、コントローラは、クラッド貯蔵タンク中のクラッド
を給水加熱器の下流側の給水中に混入させる特許請求の
範囲第１項記載の原子炉復・給水系の水質制御装置。[Scope of Claims] 1. In a water quality control device for a reactor condensing water supply system that controls the water quality of the feed water of a nuclear reactor condensing water supply system in which a hollow fiber membrane filter is applied to a condensate filter of a nuclear power plant, A crud storage tank is connected to the backwash water receiving tank of the condensate filter to store crud contained in the backwash water, and a crud storage tank is provided downstream of the high-pressure water supply pump to detect the Fe/Ni ratio in the water supply. A water quality detector and a Fe/N
A water quality control device for a reactor condensate/water supply system, comprising: a controller that mixes cladding in the cladding storage tank into the water supply when the i ratio falls below a predetermined value. 2. The water quality control device for a nuclear reactor condensate/feedwater system according to claim 1, wherein the controller mixes the crud in the crud storage tank into the feedwater upstream of the feedwater heater. 3. The water quality control device for a nuclear reactor condensate/feedwater system according to claim 1, wherein the controller mixes the crud in the crud storage tank into the feedwater downstream of the feedwater heater.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62254752A JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62254752A JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0198998A true JPH0198998A (en) | 1989-04-17 |
| JPH0721549B2 JPH0721549B2 (en) | 1995-03-08 |
Family
ID=17269387
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62254752A Expired - Lifetime JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0721549B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000121785A (en) * | 1998-10-16 | 2000-04-28 | Hitachi Ltd | Reactor power plant and its operation method |
-
1987
- 1987-10-12 JP JP62254752A patent/JPH0721549B2/en not_active Expired - Lifetime
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000121785A (en) * | 1998-10-16 | 2000-04-28 | Hitachi Ltd | Reactor power plant and its operation method |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0721549B2 (en) | 1995-03-08 |
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