JPS6258480B2 - - Google Patents
Info
- Publication number
- JPS6258480B2 JPS6258480B2 JP55093959A JP9395980A JPS6258480B2 JP S6258480 B2 JPS6258480 B2 JP S6258480B2 JP 55093959 A JP55093959 A JP 55093959A JP 9395980 A JP9395980 A JP 9395980A JP S6258480 B2 JPS6258480 B2 JP S6258480B2
- Authority
- JP
- Japan
- Prior art keywords
- gas
- water
- piping
- nuclear power
- cathode
- 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.)
- Expired
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 38
- 239000007789 gas Substances 0.000 claims description 32
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 claims description 18
- 229910001882 dioxygen Inorganic materials 0.000 claims description 18
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 16
- 238000005260 corrosion Methods 0.000 claims description 9
- 230000007797 corrosion Effects 0.000 claims description 9
- 238000009835 boiling Methods 0.000 claims description 8
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 6
- 239000001301 oxygen Substances 0.000 claims description 6
- 229910052760 oxygen Inorganic materials 0.000 claims description 6
- 238000000034 method Methods 0.000 claims description 5
- 238000005868 electrolysis reaction Methods 0.000 claims description 3
- 230000002401 inhibitory effect Effects 0.000 claims description 3
- 238000000605 extraction Methods 0.000 claims 2
- 230000001629 suppression Effects 0.000 claims 1
- 239000003792 electrolyte Substances 0.000 description 11
- 239000007864 aqueous solution Substances 0.000 description 9
- 238000002347 injection Methods 0.000 description 3
- 239000007924 injection Substances 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- VEXZGXHMUGYJMC-UHFFFAOYSA-N Hydrochloric acid Chemical compound Cl VEXZGXHMUGYJMC-UHFFFAOYSA-N 0.000 description 2
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- QOSATHPSBFQAML-UHFFFAOYSA-N hydrogen peroxide;hydrate Chemical compound O.OO QOSATHPSBFQAML-UHFFFAOYSA-N 0.000 description 1
- 238000007726 management method Methods 0.000 description 1
- 239000003595 mist Substances 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 239000000243 solution 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
Landscapes
- Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
Description
【発明の詳細な説明】
本発明は、沸騰水型原子力発電プラントにおい
て、給水系配管内へ酸素ガスを圧入して接液表面
へ酸化被膜を形成すると共に原子炉水中へ水素ガ
スを圧入して原子炉水中の溶存酸素濃度を低減さ
せることにより沸騰水型原子力発電プラントの接
液表面の腐食を抑制する方法に関する。DETAILED DESCRIPTION OF THE INVENTION In a boiling water nuclear power plant, the present invention involves pressurizing oxygen gas into the water supply system piping to form an oxide film on the liquid-contacted surface, and at the same time injecting hydrogen gas into the reactor water. The present invention relates to a method for suppressing corrosion of wetted surfaces of a boiling water nuclear power plant by reducing dissolved oxygen concentration in reactor water.
一般に、給水系配管および給水系の機器の接液
表面の腐食を抑制する目的で、接液表面へ酸化被
膜を形成することが行なわれている。このような
酸化被膜の形成は、従来給水系配管へ高圧酸素ガ
スボンベから酸素ガスを圧入するかポンピングに
より過酸化水素水を圧入することにより行なわれ
ていたが、これらの注入量を原子炉出力に比例し
て制御することが困難なうえに、酸素ガス、過酸
化水素水ともに消耗量を管理する必要があり、備
蓄場所、補給頻度、管理方法、取り扱い等が非常
に煩雑であるという難点があつた。 Generally, for the purpose of suppressing corrosion of the surfaces of water supply system piping and water supply system equipment that come into contact with liquid, an oxide film is formed on the surfaces that come into contact with liquid. Formation of such an oxide film has conventionally been done by injecting oxygen gas from a high-pressure oxygen gas cylinder into the water supply piping or by injecting hydrogen peroxide water by pumping, but these injection amounts can be adjusted to reactor output. In addition to being difficult to control proportionately, it is necessary to manage the amount of consumption of both oxygen gas and hydrogen peroxide, and there are drawbacks such as storage locations, replenishment frequency, management methods, handling, etc. are extremely complicated. Ta.
一方、原子炉圧力容器内においては、炉内構造
物の置かれる腐食雰囲気を緩和するために原子炉
水中の溶存酸素濃度を低減させる必要があり、酸
素濃度のコントロールの目的で原子炉水中へ水素
ガスボンベから水素ガスが圧入されるが、この場
合にも給水系配管への酸素ガス圧入の場合と同様
の問題が生ずる。 On the other hand, inside the reactor pressure vessel, it is necessary to reduce the dissolved oxygen concentration in the reactor water in order to alleviate the corrosive atmosphere in which the reactor internals are placed, and hydrogen is added to the reactor water for the purpose of controlling the oxygen concentration. Hydrogen gas is press-injected from a gas cylinder, but in this case as well, the same problem as in the case of pressurizing oxygen gas into water supply piping occurs.
本発明は、かかる従来の難点を解消すべくなさ
れたもので、沸騰水型原子力発電プラントにおい
て、給水系配管へ酸素ガスを圧入して接液表面へ
酸化被膜を形成すると共に原子炉水中へ水素ガス
を圧入して原子炉水中の溶存酸素濃度を抵減させ
ることにより前記プラントの接液表面の腐食を抑
制するにあたり、前記酸素ガスおよび水素ガス
を、それぞれ水電解槽の陽極ガス抽気配管および
陰極ガス抽気配管から直接供給することにより原
子力発電プラントの腐食抑制方法における叙上の
欠点を解消しようとするものである。 The present invention has been made to solve these conventional problems, and in a boiling water nuclear power plant, oxygen gas is pressurized into the water supply system piping to form an oxide film on the surface in contact with the liquid, and at the same time hydrogen is introduced into the reactor water. In suppressing corrosion of the wetted surfaces of the plant by reducing the dissolved oxygen concentration in the reactor water by pressurizing gas, the oxygen gas and hydrogen gas are supplied to the anode gas bleed pipe and the cathode of the water electrolyzer, respectively. The present invention attempts to overcome the above-mentioned drawbacks in the method of inhibiting corrosion in nuclear power plants by supplying gas directly from the bleed piping.
以下図面を参照して本発明の詳細を説明する。 The details of the present invention will be explained below with reference to the drawings.
図面は本発明に使用する電解槽およびその配管
系を示す系統図である。 The drawing is a system diagram showing an electrolytic cell and its piping system used in the present invention.
図において電解槽１には、直流電源２に可変抵
抗３を介して接続された陽電極４および陰電極５
が挿入され、かつ電解質水溶液６が充填されてい
る。 In the figure, an electrolytic cell 1 includes a positive electrode 4 and a negative electrode 5 connected to a DC power source 2 via a variable resistor 3.
is inserted and filled with an electrolyte aqueous solution 6.
この電解質水溶液は、例えば水に塩酸を溶解さ
せたもののように電解により酸素ガスと水素ガス
とを発生するものから成つている。 This electrolyte aqueous solution is made of something that generates oxygen gas and hydrogen gas by electrolysis, such as a solution in which hydrochloric acid is dissolved in water.
この電解質水溶液は、電解質水溶液供給槽７か
ら供給配管８により供給されるようになつてい
る。電解質水溶液６の供給は、電解槽１中の電解
質水溶液６が一定レベル以下になると電解槽レベ
ルスイツチ９がこれを検知して供給配管８の供給
弁１０を開放させることにより行なわれる。一定
量の電解質水溶液が供給されると供給弁１０は閉
鎖される。陽電極４および陰電極５には、それぞ
れ陽極ガス補集筒１１および陰極ガス補集筒１２
が被嵌されている。陽極ガス補集筒１１には陽極
ガス抽気管１３が接続され、この陽極ガス抽気管
１３は、ドレントラツプ１４および昇圧ポンプ１
５を経て注入ノズル１６により給水系配管１７内
へ開口している。 This electrolyte aqueous solution is supplied from an electrolyte aqueous solution supply tank 7 through a supply pipe 8 . The electrolyte aqueous solution 6 is supplied by the electrolytic cell level switch 9 detecting this when the electrolyte aqueous solution 6 in the electrolytic cell 1 falls below a certain level and opening the supply valve 10 of the supply piping 8. When a certain amount of electrolyte aqueous solution is supplied, the supply valve 10 is closed. The anode gas collection cylinder 11 and the cathode gas collection cylinder 12 are provided on the anode 4 and the cathode 5, respectively.
is fitted. An anode gas bleed pipe 13 is connected to the anode gas collection tube 11, and this anode gas bleed pipe 13 is connected to a drain trap 14 and a boost pump 1.
5 and opens into the water supply system piping 17 through an injection nozzle 16.
一方陰極ガス補集筒１２には、陰極ガス抽気配
管１８が接続され、ドレントラツプ１９および昇
圧ポンプ２０を経て図示を省略した原子炉圧力容
器又は原子炉圧力容器へ連通する他の配管内へ開
口している。なお、ドレントラツプ１４，１９
は、陽極ガスおよび陰極ガスと共に抽気された電
解質水溶液のミストによるドレンを補集するため
に設けたもので、補集されたドレンが一定レベル
以上になるとレベルスイツチ２１，２２がこれを
検出してドレン弁２３，２４を開放し、図示を省
略したドレン容器へドレンを放出させる。２５，
２６は陽極ガス抽気配管１３および陰極ガス抽気
配管１８の昇圧ポンプ１５，２０の下流へ設けら
れた三方切替弁であり、ガス注入を行なわない状
態では、それぞれの抽気ガス管１３，１８を、技
管２７，２８へ接続させて、図示を省略したガス
補集容器へ抽気ガスを送入するよう構成されてい
る。 On the other hand, a cathode gas bleed pipe 18 is connected to the cathode gas collection tube 12, and opens into the reactor pressure vessel (not shown) or another pipe communicating with the reactor pressure vessel via a drain trap 19 and a boost pump 20. ing. In addition, drain traps 14, 19
is provided to collect the drain caused by the mist of the electrolyte aqueous solution extracted together with the anode gas and the cathode gas, and when the collected drain reaches a certain level or higher, the level switches 21 and 22 detect this. The drain valves 23 and 24 are opened to discharge drain into a drain container (not shown). 25,
Reference numeral 26 denotes a three-way switching valve provided downstream of the boost pumps 15 and 20 in the anode gas bleed pipe 13 and cathode gas bleed pipe 18, and when gas is not injected, the bleed gas pipes 13 and 18 are It is connected to pipes 27 and 28 and is configured to send bleed gas to a gas collection container (not shown).
以上説明した装置を使用して本発明は次のよう
にして実施される。 The present invention is implemented as follows using the apparatus described above.
すなわち、給水系配管１７へ酸素ガスを圧入す
る場合には、三方切替弁２５，２６により陽極ガ
ス抽気配管１３を注入ノズル１６側の配管と接続
させ、陰極ガス抽気配管１８を岐管２８と接続さ
せ、陽極４、陰極５間へ直流電源２より直流電流
を流す。 That is, when pressurizing oxygen gas into the water supply system pipe 17, the anode gas bleed pipe 13 is connected to the pipe on the injection nozzle 16 side using the three-way switching valves 25 and 26, and the cathode gas bleed pipe 18 is connected to the branch pipe 28. Then, a DC current is applied between the anode 4 and the cathode 5 from the DC power supply 2.
これによつて、陽極４および陰極５からは、次
の反応
陽極；2H2O→O2↑＋4H+＋4e-
陰極；4H+＋4e-→2H2↑
により、それぞれ酸素ガスおよび水素ガスが発生
するが、このうち酸素ガスは陽極ガス抽気配管１
３を通り昇圧ポンプ１５により昇圧され給水系配
管１７へ圧入される。 As a result, oxygen gas and hydrogen gas are generated from the anode 4 and cathode 5 through the following reaction: Anode; 2H 2 O→O 2 ↑+4H + +4e - Cathode; 4H + +4e - →2H 2 ↑ However, the oxygen gas is in the anode gas bleed pipe 1.
3, the pressure is increased by a boost pump 15, and the water is pressurized into the water supply system piping 17.
給水系配管１７内へ圧入される酸素ガスの量
は、原子力出力に比例した量とされるが、圧入量
の制御は、可変抵抗３により電解電流を制御する
ことにより行なわれる。 The amount of oxygen gas injected into the water supply system piping 17 is proportional to the nuclear power output, and the amount of oxygen gas injected is controlled by controlling the electrolytic current using the variable resistor 3.
また、陰極５において発生した水素ガスは、陰
極ガス抽気配管１８を通り三方切替弁２６を経て
岐管２８へ入り陰極ガス補集容器へ補集される。 Furthermore, hydrogen gas generated at the cathode 5 passes through the cathode gas bleed pipe 18, passes through the three-way switching valve 26, enters the branch pipe 28, and is collected in the cathode gas collection container.
一方、原子炉水中へ水素ガスを圧入する場合に
は、陽極ガス抽気配管１３を岐管２７へ接続し、
陰極ガス抽気配管１８を原子炉圧力容器又は原子
炉圧力容器へ開口する他の配管へ接続された配管
２９へ接続するよう三方切替弁２５，２６を切替
えて同様の操作を行なう。この場合も水素ガスの
供給量の制御は可変抵抗３により行なうようにす
る。 On the other hand, when injecting hydrogen gas into the reactor water, connect the anode gas bleed pipe 13 to the branch pipe 27,
A similar operation is performed by switching the three-way switching valves 25 and 26 so as to connect the cathode gas bleed pipe 18 to a pipe 29 connected to the reactor pressure vessel or another pipe opening to the reactor pressure vessel. In this case as well, the amount of hydrogen gas supplied is controlled by the variable resistor 3.
以上の説明からも明らかなように、本発明にお
いては、沸騰水型原子炉において腐食抑制の目的
で給水系配管内および原子炉水中へ圧入する酸素
ガスおよび水素ガスとして、水の電気分解により
発生する酸素ガスおよび水素ガスを直接使用する
ようにしたから、補給量の制御がきわめて容易で
あり、また通常の保管は電解液の状態で行なわれ
るから、備蓄に要する占有面積もわずかで済み、
取扱いも便利である。 As is clear from the above description, in the present invention, oxygen gas and hydrogen gas generated by water electrolysis are used as oxygen gas and hydrogen gas to be injected into water supply piping and reactor water for the purpose of suppressing corrosion in a boiling water reactor. Since the oxygen and hydrogen gas used in the electrolyte are used directly, it is extremely easy to control the amount of replenishment, and since the electrolyte is normally stored, the space required for stockpiling is small.
It is also convenient to handle.
図面は、本発明に使用する電解槽およびその配
管系を示す系統図である。
１…電解槽、２…直流電源、３…可変抵抗、４
…陽電極、５…陰電極、６…電解質水溶液、１３
…陽極ガス抽気管、１７…給水系配管、１８…陰
極ガス抽気管、２５，２６…三方切替弁。
The drawing is a system diagram showing an electrolytic cell and its piping system used in the present invention. 1... Electrolytic cell, 2... DC power supply, 3... Variable resistance, 4
... Positive electrode, 5... Negative electrode, 6... Electrolyte aqueous solution, 13
... Anode gas bleed pipe, 17... Water supply system piping, 18... Cathode gas bleed pipe, 25, 26... Three-way switching valve.
Claims (1)
系配管内へ酸素ガスを圧入して接液表面へ酸化被
膜を形成すると共に原子炉水中へ水素ガスを圧入
して原子炉水中の溶存酸素濃度を低減させること
により前記プラントの接液表面の腐食を抑制する
にあたり、前記酸素ガスおよび水素ガスを、それ
ぞれ水電解槽の陽極ガス抽気配管および陰極ガス
抽気配管から直接供給することを特徴とする沸騰
水型原子力発電プラントにおける腐食抑制方法。 ２ 陽極ガス抽気配管および陰極ガス抽気配管に
は、昇圧ポンプが介挿されていることを特徴とす
る特許請求の範囲第１項記載の沸騰水型原子力発
電プラントにおける腐食抑制方法。 ３ 酸素ガスおよび水素ガスの供給量は、水電解
槽の電解電流により制御される特許請求の範囲第
１項又は第２項記載の沸騰水型原子力発電プラン
トにおける腐食抑制方法。[Claims] 1. In a boiling water nuclear power plant, oxygen gas is injected into the water supply system piping to form an oxide film on the liquid-contacted surface, and hydrogen gas is injected into the reactor water to improve the water content in the reactor water. In suppressing corrosion of the wetted surfaces of the plant by reducing the dissolved oxygen concentration, the oxygen gas and hydrogen gas are supplied directly from the anode gas bleed piping and cathode gas bleed piping of the water electrolyzer, respectively. Corrosion suppression method for boiling water nuclear power plants. 2. The method for inhibiting corrosion in a boiling water nuclear power plant according to claim 1, wherein a booster pump is inserted in the anode gas extraction piping and the cathode gas extraction piping. 3. The method for inhibiting corrosion in a boiling water nuclear power plant according to claim 1 or 2, wherein the supply amounts of oxygen gas and hydrogen gas are controlled by the electrolysis current of the water electrolyzer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9395980A JPS5719698A (en) | 1980-07-11 | 1980-07-11 | Method of protecting corrosion in bwr type atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9395980A JPS5719698A (en) | 1980-07-11 | 1980-07-11 | Method of protecting corrosion in bwr type atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5719698A JPS5719698A (en) | 1982-02-01 |
| JPS6258480B2 true JPS6258480B2 (en) | 1987-12-05 |
Family
ID=14096946
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9395980A Granted JPS5719698A (en) | 1980-07-11 | 1980-07-11 | Method of protecting corrosion in bwr type atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5719698A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01152384U (en) * | 1988-04-01 | 1989-10-20 | ||
| JPH01153656U (en) * | 1988-04-05 | 1989-10-23 |
-
1980
- 1980-07-11 JP JP9395980A patent/JPS5719698A/en active Granted
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01152384U (en) * | 1988-04-01 | 1989-10-20 | ||
| JPH01153656U (en) * | 1988-04-05 | 1989-10-23 |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5719698A (en) | 1982-02-01 |
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