JPS6098390A - Nuclear power plant - Google Patents
Nuclear power plantInfo
- Publication number
- JPS6098390A JPS6098390A JP58205764A JP20576483A JPS6098390A JP S6098390 A JPS6098390 A JP S6098390A JP 58205764 A JP58205764 A JP 58205764A JP 20576483 A JP20576483 A JP 20576483A JP S6098390 A JPS6098390 A JP S6098390A
- Authority
- JP
- Japan
- Prior art keywords
- hydrazine
- condensate
- water
- nuclear power
- ammonia
- 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
- OAKJQQAXSVQMHS-UHFFFAOYSA-N Hydrazine Chemical compound NN OAKJQQAXSVQMHS-UHFFFAOYSA-N 0.000 claims description 42
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 41
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 claims description 32
- 229910021529 ammonia Inorganic materials 0.000 claims description 16
- 238000002347 injection Methods 0.000 claims description 10
- 239000007924 injection Substances 0.000 claims description 10
- 238000001816 cooling Methods 0.000 claims description 8
- 238000010248 power generation Methods 0.000 claims description 7
- 239000000126 substance Substances 0.000 claims description 4
- 238000005260 corrosion Methods 0.000 description 10
- 230000007797 corrosion Effects 0.000 description 10
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 8
- 229910052760 oxygen Inorganic materials 0.000 description 8
- 239000001301 oxygen Substances 0.000 description 8
- 238000010612 desalination reaction Methods 0.000 description 6
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 4
- 238000000354 decomposition reaction Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 241000196324 Embryophyta Species 0.000 description 2
- 206010073306 Exposure to radiation Diseases 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910052742 iron Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- QGZKDVFQNNGYKY-UHFFFAOYSA-O Ammonium Chemical compound [NH4+] QGZKDVFQNNGYKY-UHFFFAOYSA-O 0.000 description 1
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- 235000008708 Morus alba Nutrition 0.000 description 1
- 240000000249 Morus alba Species 0.000 description 1
- 235000018821 Rhododendron arboreum Nutrition 0.000 description 1
- 244000218234 Rhododendron arboreum Species 0.000 description 1
- BLRPTPMANUNPDV-UHFFFAOYSA-N Silane Chemical compound [SiH4] BLRPTPMANUNPDV-UHFFFAOYSA-N 0.000 description 1
- 150000008064 anhydrides Chemical class 0.000 description 1
- KWYKSRAECRPMIS-UHFFFAOYSA-N azane;hydrazine Chemical compound N.NN KWYKSRAECRPMIS-UHFFFAOYSA-N 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000005115 demineralization Methods 0.000 description 1
- 230000002328 demineralizing effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 230000005693 optoelectronics Effects 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 229910000077 silane Inorganic materials 0.000 description 1
- 239000004575 stone 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
- Saccharide Compounds (AREA)
- Low-Molecular Organic Synthesis Reactions Using Catalysts (AREA)
- Steroid Compounds (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】
〔発明の技術分野〕
本発明は原子力発電プラントに関し、さらに訂しくはプ
ラント内に配置された装＠ａ３よび配管内面のｒｇ４食
が抑制された原子力発電プラン１−に関Ｊる。Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a nuclear power plant, and more particularly to a nuclear power generation plan 1- in which RG4 corrosion on the inside of the equipment and piping placed in the plant is suppressed. Seki Juru.
〔発明の技術的背景とその問題点）
一般に沸騰水形原子炉（Ｂ Ｗ Ｒ）を備え／ｊ原子力
発電設備では、その−次冷却系にお（）る復水系および
給水系の装置および配管内面に錆等の腐食生成物が光生
じ、それが散開化されて系統水内を循環Ｊるため、系統
全体が汚染され、運転員等の被爆５１吊を増加させてい
た。[Technical background of the invention and its problems] Generally, nuclear power generation facilities equipped with a boiling water reactor (BWR) require equipment and piping for the condensate system and water supply system in the secondary cooling system. Corrosion products such as rust were formed on the inner surface, which spread out and circulated within the system water, contaminating the entire system and increasing the number of people exposed to radiation by operators and others.
この被爆線量の増加を防止づるために、従来の［３Ｗ
＋＜では復水１１１２ ’塩基の下流に酸素注入して所
定の酸素を溶解させ、それににり配管内面に安定な酸化
皮膜を形成させて腐食生成物の梵１−を抑制・）る方法
がとられていた。In order to prevent this increase in exposure dose, the conventional [3W
In the case of +<, there is a method of injecting oxygen downstream of the condensate 1112' base to dissolve a certain amount of oxygen, thereby forming a stable oxide film on the inner surface of the pipe and suppressing corrosion products. It had been taken.
しかしながら、上記の給水系酸素注入（・（よ、ｉＩＪ
水脱塩堝上流側での腐食生成物の発生を防止できず、一
般に復水中の鉄ｉｌ１度（約３０１１１１）の３り％程
度（給水中鉄淵度１０ｐｐｂ Ｐｉ！度）が復水脱塩ｊ
ハ下流にリークしていた。したがって、従来の方法では
このリーク分が原子炉にそのままもも込まれ、運転員の
被爆線■を大幅に低減することはできなかった。However, the above water supply system oxygen injection (・(yo, iIJ
It is not possible to prevent the generation of corrosion products on the upstream side of the water desalination tank, and generally about 3% of the iron 1 degree (approx. 301111) in the condensate water (iron depth 10 ppb Pi! degree in the feed water) j
It was leaking downstream. Therefore, with conventional methods, this leakage is directly leaked into the reactor, making it impossible to significantly reduce radiation exposure to operators.
（発明の目的）
本発明は上記問題点を解消するためになされたもので、
その目的とするところは一次冷却系における復水１１；
２塩塔上流側および原子炉内にＪ３いてし腐食生成物の
発生を抑制でき、系内の被爆線量を大幅に低減Ｊること
のできる原子力光電ブラン１−を提供づることである。(Object of the invention) The present invention has been made to solve the above problems.
Its purpose is to condensate 11 in the primary cooling system;
It is an object of the present invention to provide a nuclear photoelectric power plant 1- which can suppress the generation of corrosion products on the upstream side of a salt tower and inside a nuclear reactor, and can significantly reduce the exposure dose within the system.
〔発明の概要］
本発明は上述の目的を達成するためになされたもので、
原子炉圧力容器の系統水流出口と系統水流入口どの間に
タービン、復水器、復水１Ｂ２ ＪＸ、ｔ ｊ？！Ｕお
よび給水加熱器を配管により順次接続させて設置した一
次冷７ＪＩ系を有Ｊ゛る原子力光電プラントにおいて、
復水脱ｊｎ塔下流側にヒドラジン、１３よびノｌンモニ
ア注入装置を設けて、系統水中にヒドラジンおよびアン
モニアを注入するようにしたことを１−■徴とするもの
である。[Summary of the invention] The present invention has been made to achieve the above objects,
Between the reactor pressure vessel system water outlet and system water inlet, turbine, condenser, condensate 1B2 JX, t j? ! In a nuclear photoelectric plant that has a primary cooling 7JI system in which U and feed water heaters are connected sequentially through piping,
The feature 1-2 is that a hydrazine, 13, and ammonia injector is installed downstream of the condensate removal tower to inject hydrazine and ammonia into the system water.
本発明においてヒドラジンは脱ｆｌｌｉ素剤として加え
るものであり、アンモニアはｐｌ−１調整剤としく加え
るものである。このヒドラジンＪ３Ｊ、びアンしニアが
注入された系統水は溶存酸素がほと／Ｖど０になり＋＋
Ｈは１０〜１１程度になる。原子力光電ノ−ノントの
主要構成材である炭素鋼、ステンレス鋼（よ高渇水中に
おいて溶存酸素の存在にＪ、り応力腐食割れ（ＳＣＣ）
を発生ずるので、系統水の水室を口のＪ：うに調整づる
ことによって、−次冷却系ＩＪおりる腐食生成物の発生
を阻止することがでさ、被爆線量を大幅に低減りること
がＣきる。In the present invention, hydrazine is added as a flll removal agent, and ammonia is added as a pl-1 regulator. The system water injected with Hydrazine J3J and Bianshinia has almost no dissolved oxygen/V0++
H will be about 10-11. Carbon steel and stainless steel, which are the main constituent materials of nuclear power optoelectronics, suffer from stress corrosion cracking (SCC) due to the presence of dissolved oxygen in high drought conditions.
Therefore, by adjusting the water chamber of the system water to the top of the cooling system, it is possible to prevent the generation of corrosion products that flow into the secondary cooling system, greatly reducing the exposure dose. C is cut.
（発明の実施例） 本発明を実施例により説明りる。(Example of the invention) The present invention will be explained by examples.
第１図は本発明の実施例である原子力発電シラン１〜の
一次冷却系を示す系統図である。FIG. 1 is a system diagram showing the primary cooling system of nuclear power generation silane 1 to which is an embodiment of the present invention.
第１図に示すように、本発明の一次冷１．ＩＩ系は原子
炉圧力容器（１）の系統水流１１冒］＜１４＞と系統水
流人口（１５）との間に順に高圧タービン（２）。As shown in FIG. 1, primary cooling 1. The II system is a high-pressure turbine (2) in order between the system water flow 11 [14] of the reactor pressure vessel (1) and the system water flow population (15).
低圧タービン（３）、主復水器（４）、低１ｆ復水ポン
プ（５）、復水脱塩塔（６）、高圧復水ポンプ（７）、
低圧給水加熱器（８）、給水ポンプ（９）’Ｊ３よび高
圧給水加熱器（１０）が配置され、復水脱塩塔（６）と
高圧復水ポンプ（７）との間にヒドラジンおよびアンモ
ニア？主人装買（１１）が設置されている。該注入装置
はヒドラジンおＪ、ひアンモニｊ′それぞれの薬注タン
クとプランジ１７一式桑注ポンプどから構成されてい（
，８１測Ｈｉｉ！ｉ’り１２）がこれに接続されている
。Low pressure turbine (3), main condenser (4), low 1f condensate pump (5), condensate desalination tower (6), high pressure condensate pump (7),
A low pressure feed water heater (8), a feed water pump (9)'J3 and a high pressure feed water heater (10) are arranged, and hydrazine and ammonia are placed between the condensate demineralization tower (6) and the high pressure condensate pump (7). ? Main equipment (11) is installed. The injection device consists of chemical injection tanks for hydrazine and ammonium, and a plunge 17 mulberry injection pump.
, 81 measurement Hii! i'ri 12) is connected to this.
原子炉圧力容器（１）で核加熱にＪ、り光ａｔ、／、：
蒸気は、高圧タービン（２）に送られ、さらに低圧ター
ビン（３〉に供給される。この但月−ターヒン（３）で
タービン買を回転させた蒸気は、主復水器（４）に送ら
れ凝縮脱気される。J, light at, /, for nuclear heating in the reactor pressure vessel (1):
The steam is sent to the high-pressure turbine (2) and further supplied to the low-pressure turbine (3).The steam that rotates the turbine in this Ta-Tahin (3) is sent to the main condenser (4). It is condensed and degassed.
主復水器（４）で凝縮された復水は、低圧復水ホン７
（５） 、 復水ｌＢ２１Ｍ塔（６） ニｍラレ、ｌｌ
１２ ｊＮ処理される。復水脱塩塔（６）で脱塩された
復水は高圧復水ポンプ（７）によって低圧給水加熱器〈
８）に送られ、加熱される。低圧給水加熱器（８）で加
熱された給水は、原子炉給水ボン／（９）によって高圧
給水加熱器（１０）を経（、原子炉圧力容器（１）に供
給される。以上の一次冷ｕＪ系において、復水脱塩塔（
６）の干流ひヒドラジンおよびアンモニアの注入装置（
１１）から系ＸＪｃ水に所定濃度のヒドラジンとアン七
ニノ７が？」−人されるようになっている。The condensate condensed in the main condenser (4) is transferred to the low pressure condensate phone 7
(5) , Condensate lB21M tower (6) Nimrare, ll
12 jN processes. The condensate desalinated in the condensate desalination tower (6) is sent to the low pressure feed water heater by the high pressure condensate pump (7).
8) and heated. The feedwater heated by the low-pressure feedwater heater (8) is supplied to the reactor pressure vessel (1) via the high-pressure feedwater heater (10) by the reactor feedwater tank (9). In the uJ system, the condensate desalination tower (
6) Drainage hydrazine and ammonia injection device (
11) From system ” - people are becoming popular.
ヒドラジンおよびアンモニアを含有した系統ホは、計測
装置（１２）によりヒドラジンＷｉ石おＪ、び１）ト１
が測定される。この計測装置は導電率８１，１１１１ｆ
ｉｌＪ３Ｊ、び酸化還元電極方式のヒドラジン分（ハ、
１１で構成されており、系統水中の導電率（μレイｍ）
、１１＋１．ヒドラジン１Ｉｉ３１１を連続測定し、イ
の出力信号をヒドラジン−アンモニア注入装置（１１）
にフィードバックし、水中のμ岨イｍ、 ｐ ｌ−１、
ヒ１〜ラジンＨ＆を所定値にコン１へロールする。The system containing hydrazine and ammonia is measured by the measuring device (12).
is measured. This measuring device has a conductivity of 81,1111f
ilJ3J, and hydrazine component of redox electrode method (c,
It is composed of 11, and the electrical conductivity in the system water (μray m)
, 11+1. Continuously measure hydrazine 1Ii311, and output the output signal of 1 to the hydrazine-ammonia injection device (11).
and give feedback to μ岨i m, p l−1 in water,
Roll Hi1 to Radin H& to a predetermined value to Con1.
このにうに所定濃度のヒドラジンＪ３よびアンしニアを
含有した系統水は低圧給水加熱器（８）を経て原子炉給
水ポンプ（９）によって畠月−給水加熱器（１０）およ
び原子炉圧力容器（１）に供給される。The system water containing a predetermined concentration of hydrazine J3 and anhydride passes through the low-pressure feedwater heater (8) and is then pumped by the reactor feedwater pump (9) to the Hatatsuki feedwater heater (10) and the reactor pressure vessel ( 1).
原子炉圧力容器（１）に供給された系統水は原子炉水と
混合され、原子炉中の溶存酸素濃度（００１１度）をは
どんどＯとし、１）１１を１０・〜１１に調整する。そ
の反応式は下記のとおりである。System water supplied to the reactor pressure vessel (1) is mixed with reactor water, and the dissolved oxygen concentration (0011 degrees) in the reactor is gradually brought to O, and 1) 11 is adjusted to 10.~11. The reaction formula is as follows.
Ｎ、Ｈ，十鈑０２→Ｎ、＋ ２１−１２０ （１）２Ｎ
よＨ６−＋Ｎ２＋Ｈ□＋２．ＮＨ，（２）ヒドラジンｌ
ｉＬ第２図に示すように １８３℃Ｃ゛分解をはじめ、
温度の上昇にともなつ”（分解率か１％：１１くなるの
で、炉内におい゛Ｃ一部分解しＣ（２）式のようにアン
モニアに変化づる。N, H, ten plates 02 → N, + 21-120 (1) 2N
YoH6-+N2+H□+2. NH, (2) hydrazine l
As shown in Figure 2 of iL, starting with decomposition at 183℃,
As the temperature rises, the decomposition rate becomes 1%:11, so C is partially decomposed in the furnace and changes to ammonia as shown in equation (2).
炉水環境に８３イＴ ハ、Ｓ ＣＣ（７） ｌｌ Ｉ：
１：ハ主１．Ｊ ｌ） ０ｉ１１度とＣ１１ｌｉ１度に
よって決定されるので、Ｄ Ｏｉｌ１度を減少するどＣ
１淵度をかなり訂容てさることとなり、Ｓ （’、 Ｃ
発生の可能性は非７＋ｆに少なくなる。In the reactor water environment 83 IT Ha, S CC (7) ll I:
1: Lord 1. J l) Since it is determined by 0i11 degree and C11li1 degree, if D Oil1 degree is decreased, C
This means that the 1-deep degree has been considerably revised, and S (', C
The probability of occurrence is reduced to non-7+f.
つぎに原子炉水中のヒドラジン、アンモニアは第３図に
示すような気液分配で主蒸気配管（１３）を通り高圧タ
ービン（２）Ｊ５よび低圧タービン（３）に送られる。Next, hydrazine and ammonia in the reactor water are sent to the high pressure turbine (2) J5 and the low pressure turbine (3) through the main steam pipe (13) in a gas-liquid distribution manner as shown in FIG.
第３図はアンモニアの気液分配率とボイラー圧力との関
係を示Ｊグラノである。Figure 3 shows the relationship between the gas-liquid distribution ratio of ammonia and the boiler pressure.
アンモニア濃度を示す。）を表わし、４ｒＡＩＩＩＩＩ
Ｉはボイラー圧力（ｋｇ７ｃｍ”）を表わづ。Indicates ammonia concentration. ), 4rAIII
I represents boiler pressure (kg7cm").
この主蒸気中に含有したヒドラジンおよびノ′ンモニｊ
７は、湿り蒸気となったタービン蒸気中の１゜レン水に
溶解し、タービントレン水の溶存酸素イルさ瓜を減少さ
せる。このタービンドレン水中の１）０澗度を減少さけ
る作用は、タービンのＳ ＣＣ防１１のため非常に効果
がある。低圧タービン（３）ニ送られたヒドラジンおよ
びアンモニア （よ二１１９水燕（４）で復水中に回収
され、復水中のｌ） Ｏｉ２度を減少さけ、復水中のｌ
）Ｈを上昇させる。これにＪ、す、復水器内小ツトウエ
ルの壁面Ｊ＞Ｊ、び復水配電にお【ノる腐食生成物の発
生を抑制りることか（く＼る。The hydrazine and monomony contained in this main steam
7 is dissolved in 1°L water in the turbine steam that has become wet steam, and reduces the amount of dissolved oxygen in the turbine train water. This action of reducing 1) 0 degrees in the turbine drain water is very effective for SCC prevention 11 of the turbine. Hydrazine and ammonia sent to the low-pressure turbine (3) (recovered in condensate by Yoji 119 Mizuen (4), l in condensate)
) Increase H. In addition, it is possible to suppress the generation of corrosion products on the wall of the small well in the condenser and on the condensate power distribution.
（発明の効果）
本発明によれば、原子力発電プラン１〜の系統水中にヒ
ドラジンおよびアンモニアが復水脱塩塔ｌ・流側におい
て注入されるので、系統水中のｌ） Ｏ１１ｉｆｆｉ度
をはどｌυどＯとし、かつｐ（−１を１０・〜１１に調
整りることができる。前記したように、高渇水中におい
てはステンレス鋼の応力腐食割れは溶存酸素濃度および
Ｃ１イＡン濃度が高い場合に箸しくなるので、本発明の
原子力光電プランｌ−ｃはＩ） ０濶度を０としたこと
により′３Ａ置内面のＩＩＩ Ｉ’Ｓを抑制ηることが
（・さ、シしたＣｌｆＡ度をか４１リム′１容（゛さる
こととなる。(Effects of the Invention) According to the present invention, hydrazine and ammonia are injected into the system water of nuclear power generation plans 1 to 1 on the condensate desalination tower l/stream side, so that the l) O11iffi degree in the system water can be reduced. and p(-1 can be adjusted to 10-11. As mentioned above, stress corrosion cracking of stainless steel occurs due to high dissolved oxygen concentration and C1 ion concentration in high drought conditions. In this case, the nuclear power photoelectric plan l-c of the present invention can suppress the IIII'S on the surface of the '3A position by setting the I)0 degree to 0. The degree will be 41 rims'1 volume.
したがつＵ ＊ ｌＦ、明の原子力光電ブラン１〜Ｍ
ｉｌｊいては、系統水中の腐食生成物の発生が抑制され
、運転員等の被爆線用を大幅に低減りることかできる。Gakatsu U * IF, Ming Nuclear Photoelectric Buran 1~M
In this case, the generation of corrosion products in the system water can be suppressed, and the exposure to radiation for operators and the like can be significantly reduced.
第１図は本発明の原子力発電ブラン１〜の一実施例の系
統図、第２図はヒドラジンの分解と温石どの関係を承り
グラフ、第３３図はアンモニアの気液分配率と圧力との
関係を示す−グラノ（・ある。
１・・・・・・１皇子炉圧力容器、２・・・・・・高圧
タービン、３・・・・・・低圧タービン、 ４・・・・
・・主復水器、５・・・・・・低圧復水ポンプ、６・・
・・・・復水脱塩１ハ、７・・・・・・高圧復水ポンプ
、８・・・・・・低ＬＬ給水加熱器、９・・・・・・原
子炉給水ポンプ、
１０・・・・・・高圧給水加熱器、
１１・・・・・・ヒドラジンおよびアンモニア１４入装
買、１２・・・・・・Ｋ１測装置、１４・・・・・・系
統水流出１１゜１５・・・・・・系統水流入口Figure 1 is a system diagram of one embodiment of the nuclear power generation system 1 to 1 of the present invention, Figure 2 is a graph showing the relationship between the decomposition of hydrazine and hot stone, and Figure 33 is the relationship between the gas-liquid partition ratio of ammonia and pressure. Indicates - Grano (There is. 1...1 Oji Reactor Pressure Vessel, 2...High Pressure Turbine, 3...Low Pressure Turbine, 4...
...Main condenser, 5...Low pressure condensate pump, 6...
...Condensate desalination 1c, 7...High pressure condensate pump, 8...Low LL feed water heater, 9...Reactor feed water pump, 10. ... High pressure water heater, 11 ... Hydrazine and ammonia 14 charged, 12 ... K1 measuring device, 14 ... System water outflow 11゜15. ...System water inlet
Claims (1)
口との間にタービン、復水器、復水脱Ｉｉ塔および給水
加熱器を配管により順次接続さＩＩＣ設置した一次冷ｆ
ＪＩ系を有づる原子力発電プランＩ〜において、復水１
１ｔｉ ｊａ塔下流側にヒドラジンおよび）７ンしニア
）主人装！６を設置したことを特徴とするＩｌｊ子力光
電プラン１〜。 （２）ヒドラジンおよびアンモニア注入装置は各薬剤用
の薬注タンクとプランジ１ノ一式薬注ポンプとから構成
′されている特ｉ′Ｆ請求範囲第１項記載の原子力発電
プランｌへ。 （３）ヒドラジンおよびアンモニア注入装置にはヒト９
９２９度およびｐＨを測定Ｊるための泪測装置が接続さ
れている特許請求範囲第１項記載の原子力発電プラン１
−０[Scope of Claims] 1) A turbine, a condenser, a condensate removal column, and a feed water heater are sequentially connected by piping between the system water outflow [21] and the system water inlet of the reactor pressure vessel. Installed primary cooling f
In nuclear power generation plan I~ with JI system, condensate 1
Hydrazine on the downstream side of the tower and near) main equipment! Ilj photoelectric plan 1~ is characterized in that 6 is installed. (2) The hydrazine and ammonia injection device is comprised of a chemical injection tank for each chemical and a plunge 1 chemical injection pump. (3) The hydrazine and ammonia injection device is
Nuclear power generation plan 1 according to claim 1, in which a measuring device for measuring 929 degrees and pH is connected.
-0
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58205764A JPS6098390A (en) | 1983-11-04 | 1983-11-04 | Nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58205764A JPS6098390A (en) | 1983-11-04 | 1983-11-04 | Nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6098390A true JPS6098390A (en) | 1985-06-01 |
Family
ID=16512277
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58205764A Pending JPS6098390A (en) | 1983-11-04 | 1983-11-04 | Nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6098390A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4820473A (en) * | 1984-11-06 | 1989-04-11 | Hitachi, Ltd. | Method of reducing radioactivity in nuclear plant |
| US4940564A (en) * | 1986-10-20 | 1990-07-10 | Hitachi, Ltd. | Suppression of deposition of radioactive substances in boiling water type, nuclear power plant |
| JP2005291815A (en) * | 2004-03-31 | 2005-10-20 | Hitachi Ltd | Methods for preventing corrosion and thinning of carbon steel |
| JP2013092392A (en) * | 2011-10-24 | 2013-05-16 | Toshiba Corp | Anticorrosion system of nuclear power plant |
-
1983
- 1983-11-04 JP JP58205764A patent/JPS6098390A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4820473A (en) * | 1984-11-06 | 1989-04-11 | Hitachi, Ltd. | Method of reducing radioactivity in nuclear plant |
| US4940564A (en) * | 1986-10-20 | 1990-07-10 | Hitachi, Ltd. | Suppression of deposition of radioactive substances in boiling water type, nuclear power plant |
| JP2005291815A (en) * | 2004-03-31 | 2005-10-20 | Hitachi Ltd | Methods for preventing corrosion and thinning of carbon steel |
| JP2013092392A (en) * | 2011-10-24 | 2013-05-16 | Toshiba Corp | Anticorrosion system of nuclear power plant |
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