JPH02167498A - Condensate cleaning device - Google Patents
Condensate cleaning deviceInfo
- Publication number
- JPH02167498A JPH02167498A JP63322852A JP32285288A JPH02167498A JP H02167498 A JPH02167498 A JP H02167498A JP 63322852 A JP63322852 A JP 63322852A JP 32285288 A JP32285288 A JP 32285288A JP H02167498 A JPH02167498 A JP H02167498A
- Authority
- JP
- Japan
- Prior art keywords
- condensate
- flow rate
- feed water
- bypass flow
- filter
- 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
- 238000004140 cleaning Methods 0.000 title abstract 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 46
- 229910052742 iron Inorganic materials 0.000 claims abstract description 30
- 238000000746 purification Methods 0.000 claims description 16
- 239000012535 impurity Substances 0.000 abstract description 10
- 238000011033 desalting Methods 0.000 abstract 1
- 238000001914 filtration Methods 0.000 abstract 1
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 22
- GUTLYIVDDKVIGB-BJUDXGSMSA-N cobalt-58 Chemical compound [58Co] GUTLYIVDDKVIGB-BJUDXGSMSA-N 0.000 description 7
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 6
- 238000010586 diagram Methods 0.000 description 4
- 239000002826 coolant Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 229910001030 Iron–nickel alloy Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 230000001629 suppression 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
- Y02E30/30—Nuclear fission reactors
Abstract
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プラント等における復水浄化装置に
係り、原子炉水中のイオン状放射能濃度の低減に関する
ものである。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a condensate purification device in a nuclear power plant or the like, and relates to reducing the concentration of ionic radioactivity in nuclear reactor water.
（従来の技術）
最近の原子力発電プラントにおける復水浄化装置では、
復水ろ過器と復水脱塩器を直列に配置した構成を採用し
ている。ここで原子炉からの復水より復水ろ過器は不溶
性不純物を、復水脱塩器においては水溶性不純物の除去
を効率良〈実施している。第２図は復水、給水系の全体
構成図で、復水器１の復水は復水ポンプ２により復水ろ
過器３に送られ、ここでろ過されるが復水ろ過器３にお
いて目詰まり等により、出入口差圧が高くなった場合に
は、復水ろ過器バイパス弁４が自動的に開き、原子炉５
への給水流量の低下を防止する。次いで復水ろ過器３を
通過した復水は復水脱塩器６を通過するが、ここでも前
記復水ろ過器３と同様に復水脱塩器バイパス弁７か設け
である。復水脱塩器６から出た復水は給水として給水ポ
ンプ７にて圧送され、給水加熱器８により昇温されて原
子炉５に送られる。原子炉５では給水が蒸気となり、タ
ービン発電機９で電気エネルギーに変換され、蒸気は復
水器１内で減圧、冷却されて再び復水となる。(Prior art) In recent condensate purification devices in nuclear power plants,
A configuration in which a condensate filter and a condensate demineralizer are arranged in series is adopted. Here, the condensate filter efficiently removes insoluble impurities from the condensate from the nuclear reactor, and the condensate demineralizer efficiently removes water-soluble impurities. Figure 2 is an overall configuration diagram of the condensate and water supply system. Condensate from the condenser 1 is sent to the condensate filter 3 by the condensate pump 2, where it is filtered. If the differential pressure at the inlet and outlet increases due to blockage, etc., the condensate filter bypass valve 4 automatically opens and the reactor 5
prevent a decrease in water supply flow rate. Next, the condensate that has passed through the condensate filter 3 passes through a condensate demineralizer 6, which is also provided with a condensate demineralizer bypass valve 7 as in the condensate filter 3. The condensate discharged from the condensate demineralizer 6 is pumped as feed water by a feed water pump 7, heated by a feed water heater 8, and sent to the reactor 5. In the nuclear reactor 5, the feed water becomes steam, which is converted into electrical energy by the turbine generator 9. The steam is depressurized and cooled in the condenser 1, and becomes condensate again.
（発明が解決しようとする課題）
上記復水浄化装置の採用により復水中に含まれたクラッ
ド鉄等が大幅に捕捉排除できたがその反面、炉水中のイ
オン状コバルト−５８やコバルト−６０の濃度か高くな
り、この結果放射能濃度が高まる問題があった。この原
因は従来炉内においてＮｉ、Ｃｏ、Ｆｅが反応し、安定
なりラッド（ＮｉＦｅ ＯＣ０Ｆｅ２０４）を生成して
２４ゝ
炉内に残留されていたものが、復水ろ過器３におけるク
ラッドの大幅捕捉によるＮｉ、Ｆｅの減少に伴い上記反
応か十分に行われず、この結果イオン状コバルト−５８
やコバル＋、−ＧＯが炉水中に増加するためで、従って
この炉水が原子炉５外の原子炉冷却材再循環系配管及び
原子炉冷却材浄化系配管等に流れて、付近の作業員に対
する被曝線量が増加するという欠点があった。(Problems to be Solved by the Invention) By adopting the above condensate purification device, clad iron contained in condensate could be largely captured and eliminated, but on the other hand, ionic cobalt-58 and cobalt-60 in the reactor water There was a problem that the radioactivity concentration increased as a result. The reason for this is that Ni, Co, and Fe react in the conventional furnace, producing stable rad (NiFe OC0Fe204), which remained in the 24゜ furnace, due to a large amount of crud being captured in the condensate filter 3. Due to the decrease in Ni and Fe, the above reaction is not carried out sufficiently, and as a result, ionic cobalt-58
This is because Kobal+, -GO increases in the reactor water, and this reactor water flows into the reactor coolant recirculation system piping and reactor coolant purification system piping outside reactor 5, causing damage to nearby workers. The disadvantage was that the exposure dose to the body increased.
本発明は上記に鑑みてなされたもので、その目的とする
ところは、復水の一部を復水ろ過器をバイパスさせて給
水中のＮ ｌ −、Ｆ ｅ濃度を調整し、このＮｉ、Ｆ
ｅに炉水中のイオン状コバルト−５８やコバルト−６０
を反応させて原子炉内に残留させ、炉外における放射能
濃度を低下して被曝を低減する復水浄化装置を提供する
ことにある。The present invention has been made in view of the above, and its purpose is to make a part of the condensate bypass the condensate filter to adjust the Nl- and Fe concentrations in the water supply, and to F
ionic cobalt-58 and cobalt-60 in the reactor water.
An object of the present invention is to provide a condensate purification device which reacts radioactive substances and causes them to remain in a nuclear reactor, thereby reducing radioactivity concentration outside the reactor and reducing exposure.
［発明の構成］
（課題を解決するための手段）
復水及び給水ラインに介挿した復水ろ過器及び復水脱塩
器と、復水ろ過器の出入口側に橋絡して設けたバイパス
流量調節弁と、前記復水ろ過器の入口側及び復水脱塩器
の出口側に設置したＮｉ、Ｆｅ濃度検出器と、この両Ｎ
ｌ ％ Ｆ ｅ濃度検出器の濃度信号から前記復水ろ
過器のＮ １ ％ Ｆ ｅ除去率の算出と復水及び給水
ラインにおけるＮｉ１Ｆｅ濃度を適切に調整するようバ
イパス流量調節弁を制御するバイパス流量演算器を具備
する。[Structure of the invention] (Means for solving the problem) A condensate filter and a condensate demineralizer inserted in a condensate and water supply line, and a bypass provided bridging the entrance and exit side of the condensate filter. A flow control valve, Ni and Fe concentration detectors installed on the inlet side of the condensate filter and the outlet side of the condensate demineralizer, and both N
Calculating the N 1 % Fe removal rate of the condensate filter from the concentration signal of the l % Fe concentration detector and controlling the bypass flow rate control valve to appropriately adjust the Ni1Fe concentration in the condensate and water supply lines. Equipped with a computing unit.
（作 用）
復水器からの復水は復水ろ過器にて不溶性不純物である
Ｎｉ、Ｆｅやクラッド等が除去され、次いて復水脱塩器
において水溶性不純物が除去された後、給水加熱器で加
熱昇温されて原子炉に給水される。この際復水ろ過器の
入口側と、復水ろ過器及び復水脱塩器の浄化装置を経由
した後の給水加熱器の入口側に設けたＮｉ、Ｆｅ濃度検
出器により、夫々におけるＮ ｌ ％ Ｆ ｅ濃度を検
出して、バイパス流量演算器において画濃度信号の偏差
から復水ろ過器を含む浄化装置におけるＮｉ、Ｆｅの除
去率を算出すると共に、給水のＮｉ、Ｆｅ濃度比率が前
記イオン状コバルト−５８やコバルト−６０を反応させ
るに適切な値で、かつ浄化機能を損なわない必要最低限
のバイパス流量を演算して、バイパス流量調節弁の開度
を制御し、給水におけるＮｉ、Ｆｅ濃度を調整する。(Function) The condensate from the condenser is passed through a condensate filter to remove insoluble impurities such as Ni, Fe, and crud, and then to a condensate demineralizer to remove water-soluble impurities. The water is heated to a higher temperature by a heater and then supplied to the reactor. At this time, Ni and Fe concentration detectors installed at the inlet side of the condensate filter and at the inlet side of the feed water heater after passing through the condensate filter and condensate demineralizer purification devices are used to detect Nl in each. % Fe concentration is detected, and the bypass flow rate calculator calculates the removal rate of Ni and Fe in the purification device including the condensate filter from the deviation of the image concentration signal, and also calculates the Ni and Fe concentration ratio of the feed water from the deviation of the image concentration signal. By calculating the minimum necessary bypass flow rate that is appropriate for reacting cobalt-58 and cobalt-60 and does not impair the purification function, the opening degree of the bypass flow rate control valve is controlled, and Ni, Fe in the water supply is controlled. Adjust concentration.
（実施例） 本発明の一実施例を図面を参照して説明する。(Example) An embodiment of the present invention will be described with reference to the drawings.
なお上記した従来技術と同じ構成部分については同一符
号を付し、詳細な説明は省略する。第１図は復水、給水
系の全体構成図で、復水器１の復水は復水ポンプ２によ
り不溶性不純物の除去を行う復水ろ過器３に送られ、次
いで水溶性不純物の除去を行う復水脱塩器６を経由した
後、給水ポンプ８にて給水加熱器９に圧送され、加熱昇
温されて原子炉５に給水される。原子炉５では蒸気とな
りタービン発電機１０で電気エネルギーに変換され、蒸
気は復水器１内で減圧、冷却されて再び復水となる。復
水ろ過器３の人口側と復水脱塩器６の出口側には夫々Ｎ
ｉ５Ｆｅ濃度検出器１１．１２が設けられている。また
復水ろ過器３を橋絡してバイパス流量調節弁１３と、復
水脱塩器６を橋絡したバイパス弁１４が配設してあり、
さらに前記２つのＮｉ１Ｆｅ濃度検出器１１．１２の出
力信号を入力して、復水ろ過器３におけるＮｉ、Ｆｅの
除去率を算出し、給水のＮｉ、Ｆｅ濃度比率が適切とな
るよう前記バイパス流量調節弁１３を制御するバイパス
流量演算器１５を設置して構成する。Note that the same components as those in the prior art described above are given the same reference numerals, and detailed explanations will be omitted. Figure 1 is an overall configuration diagram of the condensate and water supply system. Condensate from condenser 1 is sent by condensate pump 2 to condensate filter 3, which removes insoluble impurities, and then to remove water-soluble impurities. After passing through the condensate demineralizer 6, the water is pumped to the feed water heater 9 by the feed water pump 8, heated and heated, and then supplied to the nuclear reactor 5. In the nuclear reactor 5, the steam becomes steam, which is converted into electrical energy by the turbine generator 10. The steam is depressurized and cooled in the condenser 1, and becomes condensate again. N is installed on the population side of the condensate filter 3 and the outlet side of the condensate demineralizer 6, respectively.
An i5Fe concentration detector 11.12 is provided. In addition, a bypass flow control valve 13 is provided that bridges the condensate filter 3, and a bypass valve 14 that bridges the condensate desalination device 6.
Furthermore, the output signals of the two Ni1Fe concentration detectors 11 and 12 are input to calculate the removal rate of Ni and Fe in the condensate filter 3, and the bypass flow rate is adjusted so that the Ni and Fe concentration ratio of the feed water is appropriate. A bypass flow rate calculator 15 that controls the control valve 13 is installed and configured.
次に上記構成による作用について説明する。復水器１か
らの復水は復水ポンプ２により先ず復水ろ過器３に送ら
れて不溶性不純物であるＮｉ１Ｆｅやクラッド等が除去
される。次いで復水脱塩器６において水溶性不純物が除
去された後、給水ポンプ８にて給水加熱器９に圧送され
て加熱昇温された後に原子炉５に給水される。原子炉５
では蒸気となりタービン発電機１０を経由して再び復水
器１に戻る。復水ろ過器３の人口側に設けたＮｉ、Ｆｅ
濃度検出器１１は常時ろ過器における復水のＮｉ、Ｆｅ
濃度を測定し、また浄化装置を経由した後の給水のＮｉ
５Ｆｅ濃度も給水ポンプ８の出口側でＮｉ、Ｆｅ濃度検
出器１１により常に検出して、いずれの信号もバイパス
流量演算器１５に出力する。バイパス流量演算器１５に
おいては両Ｎｉ１Ｆｅ濃度検出器１１．１２からの濃度
信号の偏差により復水ろ過器３を含む浄化装置における
Ｎｉ１Ｆｅの除去率を算出すると共に、給水のＮｉ。Next, the effect of the above configuration will be explained. Condensate from the condenser 1 is first sent to a condensate filter 3 by a condensate pump 2 to remove insoluble impurities such as Ni1Fe and crud. Next, water-soluble impurities are removed in a condensate demineralizer 6, and then the water is pumped to a feed water heater 9 by a feed water pump 8, heated and heated, and then supplied to the nuclear reactor 5. reactor 5
Then, it becomes steam and returns to the condenser 1 again via the turbine generator 10. Ni, Fe installed on the artificial side of the condensate filter 3
The concentration detector 11 constantly detects Ni and Fe in the condensate in the filter.
Measuring the concentration of Ni in the feed water after passing through the purification device
The 5Fe concentration is also constantly detected by the Ni and Fe concentration detector 11 on the outlet side of the water supply pump 8, and both signals are output to the bypass flow rate calculator 15. The bypass flow rate calculator 15 calculates the Ni1Fe removal rate in the purification device including the condensate filter 3 based on the deviation of the concentration signals from both Ni1Fe concentration detectors 11 and 12, and also calculates the Ni1Fe removal rate in the water supply water.
Ｆｅ濃度比率が前記イオン状コバルト−５８やコバルト
６０を反応させるに適切な値で、かつ浄化機能を損なわ
ない必要最低限のバイパス流量を演算して、前記バイパ
ス流量調節弁１３の開度を制御する。The opening degree of the bypass flow rate control valve 13 is controlled by calculating the necessary minimum bypass flow rate at which the Fe concentration ratio is an appropriate value for reacting the ionic cobalt-58 and cobalt-60 and which does not impair the purification function. do.
これにより復水は復水ろ過器３及び復水脱塩器６の浄化
装置を通過する間に、従来と略同様の浄化かなされて給
水としての水質の向上、維持をすると共に、Ｎｉ、Ｆｅ
濃度を適切に調整して原子炉５に給水される。従ってこ
の給水中のＮｉ、Ｆｅは、原子炉５内においてイオン状
コバルト−５８やコバルト−６０が抽出されても、これ
と直ちに反応してクラッド化し炉内に捕捉固定されるの
で、炉水中のイオン状コバルト−５８やコバルト−６０
による放射能濃度か低下し、この結果炉水が前記の原子
炉冷却材再循環系配管及び原子炉冷抑制浄化系配管等に
流れても付近の被曝線量を増加させることがない。As a result, while the condensate passes through the condensate filter 3 and the condensate demineralizer 6 purification devices, it is purified in substantially the same manner as in the past, improving and maintaining the water quality as water supply, and removing Ni, Fe, etc.
The water is supplied to the reactor 5 with its concentration adjusted appropriately. Therefore, even if ionized cobalt-58 and cobalt-60 are extracted in the reactor 5, Ni and Fe in this feed water immediately react with them to form a cladding and are captured and fixed in the reactor. Ionic cobalt-58 and cobalt-60
As a result, even if reactor water flows into the reactor coolant recirculation system piping, reactor cold suppression purification system piping, etc., the radiation exposure dose in the vicinity will not increase.
［発明の効果］
以上本発明によれば、復水ろ過器を含めた浄化装置の浄
化機能を低下することなく、炉水中のイオン状放射能濃
度を低下して原子炉周辺における作業員の被曝低減と、
水質改善の自動化により運転員の負担を軽減する効果が
ある。[Effects of the Invention] According to the present invention, the concentration of ionic radioactivity in reactor water can be reduced and the exposure of workers around the reactor can be reduced without reducing the purification function of the purification device including the condensate filter. reduction and
Automating water quality improvement has the effect of reducing the burden on operators.
第１図は本発明採用の復水、給水系の全体構成図、第２
図は従来の復水、給水系の全体構成図である。
１・・・復水器、 ３・・・復水ろ過器、５・・・原子
炉、 ６・・・復水脱塩器、１１．１２−Ｎ ｉ 、
Ｆ ｅ濃度検出器、１３・・・バイパス流量調節弁、
１５・・・バイパス流量演算器。
代理人 弁理士 大 胡 典 夫
第
図Figure 1 is an overall configuration diagram of the condensate and water supply system adopted by the present invention;
The figure is an overall configuration diagram of a conventional condensate and water supply system. 1... Condenser, 3... Condensate filter, 5... Nuclear reactor, 6... Condensate demineralizer, 11.12-N i,
F e concentration detector, 13... Bypass flow rate control valve, 15... Bypass flow rate calculator. Agent Patent Attorney Norifu Ogo
Claims (1)
復水ろ過器及び復水脱塩器と、前記復水ろ過器の出入口
側に橋絡して設けたバイパス流量調節弁と、前記復水ろ
過器の入口側及び復水脱塩器の出口側に設置したＮｉ、
Ｆｅ濃度検出器と、この両Ｎｉ、Ｆｅ濃度検出器の濃度
信号から前記復水ろ過器のＮｉ、Ｆｅ除去率の算出と復
水及び給水ラインにおけるＮｉ、Ｆｅ濃度を適切に調整
するようバイパス流量調節弁を制御するバイパス流量演
算器からなることを特徴とする復水浄化装置。A condensate filter and a condensate demineralizer inserted in a condensate and water supply line of a nuclear power plant, etc., a bypass flow rate control valve provided in a bridge on the inlet/outlet side of the condensate filter, and the condensate Ni installed on the inlet side of the filter and the outlet side of the condensate demineralizer,
Calculate the Ni and Fe removal rate of the condensate filter from the Fe concentration detector and the concentration signals of both Ni and Fe concentration detectors, and adjust the bypass flow rate to appropriately adjust the Ni and Fe concentrations in the condensate and water supply lines. A condensate purification device comprising a bypass flow rate calculator that controls a control valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63322852A JPH02167498A (en) | 1988-12-21 | 1988-12-21 | Condensate cleaning device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63322852A JPH02167498A (en) | 1988-12-21 | 1988-12-21 | Condensate cleaning device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02167498A true JPH02167498A (en) | 1990-06-27 |
Family
ID=18148320
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63322852A Pending JPH02167498A (en) | 1988-12-21 | 1988-12-21 | Condensate cleaning device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02167498A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6088417A (en) * | 1996-04-01 | 2000-07-11 | Siemens Aktiengesellschaft | Apparatus and method for leak detection |
| JP2014115110A (en) * | 2012-12-06 | 2014-06-26 | Toshiba Corp | α NUCLIDE SEPARATION METHOD FROM SODIUM CHLORIDE-CONTAINING WASTE LIQUID, AND α NUCLIDE SEPARATION SYSTEM FROM SODIUM CHLORIDE-CONTAINING WASTE LIQUID |
-
1988
- 1988-12-21 JP JP63322852A patent/JPH02167498A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6088417A (en) * | 1996-04-01 | 2000-07-11 | Siemens Aktiengesellschaft | Apparatus and method for leak detection |
| JP2014115110A (en) * | 2012-12-06 | 2014-06-26 | Toshiba Corp | α NUCLIDE SEPARATION METHOD FROM SODIUM CHLORIDE-CONTAINING WASTE LIQUID, AND α NUCLIDE SEPARATION SYSTEM FROM SODIUM CHLORIDE-CONTAINING WASTE LIQUID |
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