JPS61162798A - Boiling water cooling type reactor - Google Patents
Boiling water cooling type reactorInfo
- Publication number
- JPS61162798A JPS61162798A JP60003335A JP333585A JPS61162798A JP S61162798 A JPS61162798 A JP S61162798A JP 60003335 A JP60003335 A JP 60003335A JP 333585 A JP333585 A JP 333585A JP S61162798 A JPS61162798 A JP S61162798A
- Authority
- JP
- Japan
- Prior art keywords
- water
- reactor
- hydrogen
- boiling water
- oxygen
- 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
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
- Physical Or Chemical Processes And Apparatus (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】 〔発明の利用分野〕 本発明は沸騰水冷却盤原子炉に係り、特に復水。[Detailed description of the invention] [Field of application of the invention] TECHNICAL FIELD The present invention relates to boiling water cooling plate reactors, particularly condensing water reactors.
給水系の炭素鋼防食用として酸素注入を、また原子炉冷
却系のステンレス鋼応力腐食割れ対策として水素注入を
実施するプラントに適用するに好適な沸騰水冷却温原子
炉に関する。The present invention relates to a boiling water-cooled hot nuclear reactor suitable for application to plants in which oxygen injection is carried out to prevent corrosion of carbon steel in the water supply system, and hydrogen injection is carried out to prevent stress corrosion cracking of stainless steel in the reactor cooling system.
沸騰水冷却温原子炉の系統構成の従来例を第１図に示す
。A conventional example of the system configuration of a boiling water cooled nuclear reactor is shown in FIG.
原子炉圧力容器１内で加圧され、沸騰した冷却水は蒸気
ドラム２で気水分離される。水は再循環ポンプ３で加圧
され原子炉圧力容器内へ戻される。Cooling water that is pressurized and boiled within the reactor pressure vessel 1 is separated into steam and water by a steam drum 2. The water is pressurized by the recirculation pump 3 and returned to the reactor pressure vessel.
蒸気はタービン系へ行き、タービン４を駆動し、復水器
５内で凝縮され、復水ポンプ６、復水脱塩器７、給水加
熱器８、・給水ポンプ９、などを経て蒸気ドラムへ戻る
。復水系、給水系は主として炭素鋼で構成され、その防
食用として復水脱塩器出口に酸素注入装置１０を設置し
、酸素注入を行っている。また、原子炉冷却系は主とし
てステンレス鋼で構成され、その応力腐食割れ対策とし
て、給水加熱器の上流側に水素注入設備１１を設置し、
水素注入を行う方法が有効とされる。The steam goes to the turbine system, drives the turbine 4, is condensed in the condenser 5, passes through the condensate pump 6, condensate demineralizer 7, feed water heater 8, feed water pump 9, etc. to the steam drum. return. The condensate system and the water supply system are mainly constructed of carbon steel, and for corrosion protection, an oxygen injection device 10 is installed at the outlet of the condensate demineralizer to inject oxygen. In addition, the reactor cooling system is mainly composed of stainless steel, and as a countermeasure against stress corrosion cracking, hydrogen injection equipment 11 is installed upstream of the feed water heater.
Hydrogen injection is considered to be an effective method.
一方、主蒸気系を流″れる蒸気中には、炉水の放射線分
解により、酸素及び水素が含まれてお°９、復水系、給
水系炭素鋼の防食用及び原子炉冷却系ステンレス鋼の応
−力腐食割れ対策として利用することが考えられるが、
□タービン上流で取シ出すと、プラント熱効率が低下す
るという欠点、またオフガス系から取り出すと、復水器
への空気もれこみがろるため、通常、酸素、水素と窒素
の分離操作が必要となり、複雑な設備が必要となる欠点
があった。On the other hand, the steam flowing through the main steam system contains oxygen and hydrogen due to radiolysis of the reactor water. It may be used as a countermeasure against stress corrosion cracking, but
□ If extracted upstream of the turbine, the plant thermal efficiency will decrease, and if extracted from the off-gas system, air may leak into the condenser, so it is usually necessary to separate oxygen, hydrogen, and nitrogen. This had the disadvantage of requiring complicated equipment.
本発明の目的は、炉水の放射線分解により生じた酸素及
び水素を、もれこみ空気との分離操作なしで、給水及び
炉水の水質調整用として、再利用可能くした沸騰水冷却
温原子炉を提供するものである。The object of the present invention is to provide a boiling water-cooled hot atom that makes it possible to reuse oxygen and hydrogen generated by radiolysis of reactor water for water quality adjustment of feed water and reactor water without the need for separation from leaked air. It provides a furnace.
本発明は、復水器への空気もれこみを防ぐことにより、
タービン系よジオ７ガス系へ流入する非凝縮性ガスを、
炉水の放射線分解くよ）生じた酸素及び水素だけとし、
このガスともれこみ空気との分離操作なしで、給水及び
炉水の水質ｆＡ整用として再利用するようにしたもので
あシ、注入ガス量の低減、希ガスホールドアツプ設備１
３の縮小をはかるものである。The present invention prevents air from leaking into the condenser.
The non-condensable gas flowing from the turbine system to the Geo 7 gas system is
(radiolysis of reactor water) only the generated oxygen and hydrogen,
This gas is designed to be reused for water supply and reactor water quality control without the need for separation from leaked air, reducing the amount of injected gas, and rare gas hold-up equipment 1.
3.
本発明を適用した沸騰水冷却温原子炉の系統構成を第２
図に示す。The system configuration of a boiling water-cooled nuclear reactor to which the present invention is applied is shown in a second diagram.
As shown in the figure.
給水及び炉水の水質調整用とし、給水中へ注入する酸素
及び水素量は、復水及び給水系の炭素鋼の防食用として
酸素５０〜ｔｏｏｐｐｂ程度、原子炉冷却系のステンレ
ス鋼の応力腐食割れ対策として水素５００ｐｐｂ程度で
ある。The amount of oxygen and hydrogen injected into the water supply is for water quality adjustment of the water supply and reactor water, and the amount of oxygen and hydrogen injected into the water supply is approximately 50 to 10 ppb to prevent corrosion of the carbon steel in the condensate and water supply systems, and to prevent stress corrosion cracking of the stainless steel in the reactor cooling system. As a countermeasure, the amount of hydrogen is approximately 500 ppb.
また、王妃の給水条件の場合に、主蒸気中の酸素及び水
素濃度は、それぞれ約１００００ｐｐｂ。Furthermore, in the case of the queen's water supply conditions, the oxygen and hydrogen concentrations in the main steam are each about 10,000 ppb.
１０００ Ｐ ９ ｂ程度と予想され、復水器からの空
気もれこみを遮断すると、これが、そのままオフガス系
へ移行するので、オフガス系、再結合器１２の前でオフ
ガスの１−を抽気し、これと水素注入設備１１よシの給
水中濃度で４９０ｐｐｂ分の水素を給水中に注入すれば
、給水中酸氷、水素、をそれぞれ１００，５００ｐｐｂ
程度にすることができる。It is expected to be about 1000 P 9 b, and when the air leakage from the condenser is blocked, this will directly transfer to the off-gas system, so the off-gas 1- is extracted from the off-gas system in front of the recombiner 12. If 490 ppb of hydrogen is injected into the feed water at a concentration of 490 ppb in the feed water from this and the hydrogen injection equipment 11, the acid ice and hydrogen in the feed water will be 100,500 ppb each.
It can be done to a certain extent.
本発明で、空気もれこみ防止法としては、水封。In the present invention, water sealing is used as a method for preventing air leakage.
シール溶接等が考えられ、第２図には復水器の外側に水
を張シ水封する例を示した。Seal welding, etc., can be considered, and Figure 2 shows an example of water sealing by filling the outside of the condenser with water.
本発明によれば、炉水の放射線分解によυ生じた酸素及
び水素を空気との分離操作なしで、給水及び炉水の水質
調整用として再利用できる効果がある。According to the present invention, oxygen and hydrogen produced by radiolysis of reactor water can be reused for water quality adjustment of feed water and reactor water without the need for separation from air.
また、オフガス中に空気の混入がなく、炉心部から運ば
れた非凝縮性の酸素、水素も、そのほとんどが、結合器
１２で水として除去できるので、通常運転時、スタック
１４から放出されるガス量が極めて少なくなシ、希ガス
ホールドホールドアツプ設備１３の容量も減少できると
いう効果がある。In addition, there is no air mixed in the off-gas, and most of the non-condensable oxygen and hydrogen carried from the reactor core can be removed as water in the coupler 12, so that they are released from the stack 14 during normal operation. Since the amount of gas is extremely small, the capacity of the rare gas hold-up equipment 13 can also be reduced.
第１図は沸騰水冷却温原子炉の系・統構成の従来例を示
す系統図、第２図は本発明を適用した沸騰水冷却温原子
炉の系統構成の一実施例を示す系統図である。
５・・・復水器、１１・・・水素注入設備、１２・・・
オフガス系再結合器、１３・・・希ガスホールドホール
ドアツプ設備、１４・・・スタック。Figure 1 is a system diagram showing a conventional example of the system configuration of a boiling water cooled nuclear reactor, and Figure 2 is a system diagram showing an example of the system configuration of a boiling water cooled nuclear reactor to which the present invention is applied. be. 5... Condenser, 11... Hydrogen injection equipment, 12...
Off-gas system recombiner, 13... Rare gas hold hold up equipment, 14... Stack.
Claims (1)
及び炉水の水質調整用として、再利用する沸騰水冷却温
原子炉において、復水器への空気もれこみを防止するこ
とにより、前記、酸素及び水素をもれこみ空気との分離
操作なしで、再利用可能にしたことを特徴とする沸騰水
冷却型原子炉。1. By preventing air leakage into the condenser in a boiling water cooled nuclear reactor where oxygen and hydrogen produced by radiolysis of reactor water are reused for water supply and water quality adjustment of the reactor water, The boiling water-cooled nuclear reactor described above is characterized in that oxygen and hydrogen can be reused without leaking and separating them from air.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60003335A JPS61162798A (en) | 1985-01-14 | 1985-01-14 | Boiling water cooling type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60003335A JPS61162798A (en) | 1985-01-14 | 1985-01-14 | Boiling water cooling type reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS61162798A true JPS61162798A (en) | 1986-07-23 |
Family
ID=11554480
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60003335A Pending JPS61162798A (en) | 1985-01-14 | 1985-01-14 | Boiling water cooling type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61162798A (en) |
-
1985
- 1985-01-14 JP JP60003335A patent/JPS61162798A/en active Pending
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