JPH027440B2 - - Google Patents
Info
- Publication number
- JPH027440B2 JPH027440B2 JP56042512A JP4251281A JPH027440B2 JP H027440 B2 JPH027440 B2 JP H027440B2 JP 56042512 A JP56042512 A JP 56042512A JP 4251281 A JP4251281 A JP 4251281A JP H027440 B2 JPH027440 B2 JP H027440B2
- Authority
- JP
- Japan
- Prior art keywords
- hydrogen
- condenser
- water
- condensate
- turbine
- 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 - Lifetime
Links
- 239000001257 hydrogen Substances 0.000 claims description 77
- 229910052739 hydrogen Inorganic materials 0.000 claims description 77
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 73
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 40
- 239000012528 membrane Substances 0.000 claims description 23
- 239000007789 gas Substances 0.000 claims description 20
- 238000011084 recovery Methods 0.000 claims description 14
- 238000009835 boiling Methods 0.000 claims description 4
- 239000012466 permeate Substances 0.000 claims description 2
- KDLHZDBZIXYQEI-UHFFFAOYSA-N Palladium Chemical compound [Pd] KDLHZDBZIXYQEI-UHFFFAOYSA-N 0.000 description 19
- 239000002826 coolant Substances 0.000 description 17
- 239000000498 cooling water Substances 0.000 description 11
- 238000010586 diagram Methods 0.000 description 10
- 229910052763 palladium Inorganic materials 0.000 description 9
- 238000010521 absorption reaction Methods 0.000 description 8
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 8
- 239000001301 oxygen Substances 0.000 description 8
- 229910052760 oxygen Inorganic materials 0.000 description 8
- 238000000746 purification Methods 0.000 description 6
- 150000002431 hydrogen Chemical class 0.000 description 5
- 239000000284 extract Substances 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 239000000956 alloy Substances 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 238000003608 radiolysis reaction Methods 0.000 description 2
- 239000002344 surface layer Substances 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229910052737 gold Inorganic materials 0.000 description 1
- 239000010931 gold Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000002401 inhibitory effect Effects 0.000 description 1
- JRTYPQGPARWINR-UHFFFAOYSA-N palladium platinum Chemical compound [Pd].[Pt] JRTYPQGPARWINR-UHFFFAOYSA-N 0.000 description 1
- SWELZOZIOHGSPA-UHFFFAOYSA-N palladium silver Chemical compound [Pd].[Ag] SWELZOZIOHGSPA-UHFFFAOYSA-N 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 230000035699 permeability Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000001737 promoting effect 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
Landscapes
- Separation Using Semi-Permeable Membranes (AREA)
Description
【発明の詳細な説明】
本発明は原子炉冷却材に水素を注入して成る原
子力プラントに係り、更に詳しくは原子炉冷却材
から逸出する水素を該冷却材に循環再注入して成
る原子力プラントに関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear power plant in which hydrogen is injected into a nuclear reactor coolant, and more particularly relates to a nuclear power plant in which hydrogen escaping from a reactor coolant is circulated and re-injected into the coolant. Regarding plants.
沸騰水形原子炉は、原子炉圧力容器内の炉心部
に配置されて核分裂を起こしている燃料棒を前記
炉心部を浸漬している通常純水から成る原子炉冷
却材で冷却すると共に、この冷却水が加熱されて
発生した蒸気を直接タービンに供給して発電して
いる。タービンを通過した蒸気は復水器で凝縮さ
れた後、復水・給水系統を介して前記圧力容器内
に戻され、原子炉冷却材として再利用される。 In a boiling water reactor, the fuel rods, which are placed in the core of the reactor pressure vessel and undergoing nuclear fission, are cooled by a reactor coolant consisting of usually pure water that immerses the core. The steam generated by heating the cooling water is supplied directly to the turbine to generate electricity. The steam that has passed through the turbine is condensed in a condenser, then returned to the pressure vessel via a condensate/water supply system and reused as reactor coolant.
ところで、この原子炉圧力容器内では、冷却水
の放射線分解につて生成した酸素や、給水中に溶
存していた酸素が冷却水と接触している構造部材
を腐食し、該部材表面に酸化皮膜を形成させ、或
は該部材の応力腐食割れの原因となるなどしてい
た。更には、該部材表面から剥離した酸化物が燃
料棒表面に沈着し、これが核反応熱の冷却水への
伝達を阻害し、プラントの発電効率を低下せしめ
ていた。 By the way, in this reactor pressure vessel, oxygen generated during the radiolysis of cooling water and oxygen dissolved in the water supply corrode the structural members that are in contact with the cooling water, forming an oxide film on the surface of the members. or cause stress corrosion cracking of the member. Furthermore, oxides separated from the surfaces of the members were deposited on the surfaces of the fuel rods, which obstructed the transfer of nuclear reaction heat to the cooling water and reduced the power generation efficiency of the plant.
これらの対策として、冷却水中の溶存酸素量を
低減せしめる目的で該冷却水中に常時水素を注入
する方法が知られている。この方法によれば、冷
却水中の溶存水素が常時高濃度に保たれている為
に、水の放射線分解により生成した、或は給水中
に溶存していた酸素は2H2＋O2→2H2Oなる反応
により水を生成して減少し、従つて冷却水に接触
している構造部材の腐食は抑制され、酸化物によ
る燃料棒の汚染も低減されることとなる。 As a countermeasure against these problems, a method is known in which hydrogen is constantly injected into the cooling water for the purpose of reducing the amount of dissolved oxygen in the cooling water. According to this method, since the dissolved hydrogen in the cooling water is always kept at a high concentration, the oxygen generated by radiolysis of water or dissolved in the water supply is 2H 2 + O 2 → 2H 2 O This reaction produces and reduces water, thus inhibiting corrosion of structural members in contact with the cooling water and reducing contamination of the fuel rods with oxides.
ところが、冷却水に注入された水素は、水蒸気
と比較して軽い為に冷却水中に止まり難く、そこ
で溶存酸素量と比較して可成過剰の量を注入する
必要があるのだが、この過剰の水素が圧力容器内
の構造部材に吸収されて該部材の水素脆化を引起
こし、或は冷却材から逸出した水素が蒸気と共に
タービンに供給されて該タービンの水素脆化を促
進するという不都合があつた。 However, since the hydrogen injected into the cooling water is lighter than water vapor, it is difficult for it to stay in the cooling water, so it is necessary to inject a considerable amount in excess compared to the amount of dissolved oxygen. The disadvantage is that hydrogen is absorbed into structural components within the pressure vessel, causing hydrogen embrittlement of the components, or that hydrogen escaping from the coolant is supplied to the turbine with steam, promoting hydrogen embrittlement of the turbine. It was hot.
従来、原子炉冷却材から逸出した水素は、通常
復水器内のガス成分を導出している副動力系にお
いて処理されていた。即ち、この副動力系は、復
水器内のガス成分を抽出する空気抽出器、及び該
空気抽出器に続く再結合器、排ガス復水器などか
ら構成されており、タービン排蒸気と共に復水器
内に導入された水素は、空気抽出器により抽出さ
れた後、再結合器により前記ガス成分に含有され
る酸素と結合され、生成した水蒸気を排ガス復水
器により凝縮されるなどして処理されていた。 In the past, hydrogen escaping from the reactor coolant was typically treated in an auxiliary power system that derived gas components within the condenser. That is, this auxiliary power system consists of an air extractor that extracts the gas components in the condenser, a recombiner following the air extractor, an exhaust gas condenser, etc., and extracts the condensate together with the turbine exhaust steam. After the hydrogen introduced into the vessel is extracted by an air extractor, it is combined with the oxygen contained in the gas component by a recombiner, and the generated water vapor is condensed by an exhaust gas condenser. It had been.
ところが、前述した冷却水に常時水素を注入す
る方法においては、タービン排蒸気中に過剰の水
素が含まれており再結合器により処理しきれない
水素が、排ガス中に可燃限界を超える濃度まで含
有され、これにより爆発の危険性を伴い、或は前
記副動力系の下流部に設けられた希ガス処理設備
に排出されて、処理される排ガス量を増大せしめ
るなどの不都合であつた。 However, in the method of constantly injecting hydrogen into the cooling water described above, the turbine exhaust steam contains excess hydrogen that cannot be processed by the recombiner, and the hydrogen contained in the exhaust gas reaches a concentration that exceeds the flammability limit. This poses a risk of explosion or is inconvenient, such as increasing the amount of exhaust gas to be treated by being discharged to rare gas treatment equipment provided downstream of the auxiliary power system.
本発明者等は、原子炉冷却材に水素を注入して
成る原子力プラントが有していた上述の不都合を
解消すべく鋭意研究した結果、復水器内のガス成
分を導出している副動力系に、前記ガス成分に含
有される水素を選択的に回収する装置を備えると
共に、この回収装置により回収される水素を原子
炉冷却材に循環再注入することにより、注入水素
を有効利用することができ、また原子炉冷却材中
の水素濃度を調節することができ、従つて前述し
たプラント構成部材の水素脆化が低減できること
を見出し、本発明を完成するに至つた。 The inventors of the present invention have conducted extensive research in order to resolve the above-mentioned disadvantages of nuclear power plants that inject hydrogen into the reactor coolant, and have discovered that the auxiliary power that derives the gas components in the condenser The system is equipped with a device for selectively recovering hydrogen contained in the gas component, and the hydrogen recovered by the recovery device is circulated and re-injected into the reactor coolant, thereby making effective use of the injected hydrogen. The present inventors have discovered that the hydrogen concentration in the reactor coolant can be adjusted and that the hydrogen embrittlement of the aforementioned plant components can be reduced, and the present invention has been completed.
本発明の目的は、原子炉構造部材の酸化を防止
するために原子炉冷却材に注入された水素が該冷
却材に循環再利用され、従つて、注入水素が有効
利用されると共に冷却材中の水素濃度が調節され
て、プラント構成部材の水素脆化が低減されてい
る原子力プラントを提供することにある。 An object of the present invention is to circulate and reuse hydrogen injected into the reactor coolant in order to prevent oxidation of reactor structural members. An object of the present invention is to provide a nuclear power plant in which hydrogen embrittlement of plant constituent members is reduced by adjusting the hydrogen concentration of the plant.
即ち、本発明の原子力プラントは、沸騰水形原
子炉の圧力容器に一端を接続する主蒸気管と、該
主蒸気管の他端に接続されるタービンと、該ター
ビンに続く復水器と、該復水器により凝縮される
水を前記の圧力容器に供給する復水・給水系統か
ら成る動力系；及び、
前記の復水器内のガス成分を導出し、含有され
る水素を選択的に透過する膜から構成される水素
回収装置を具備する副動力系；
を備えている原子力プラントであつて、
前記の水素回収装置により回収さる水素の導管
が前記の復水・給水系統に接続されていることを
特徴とするものである。 That is, the nuclear power plant of the present invention includes a main steam pipe having one end connected to the pressure vessel of the boiling water reactor, a turbine connected to the other end of the main steam pipe, and a condenser following the turbine. A power system consisting of a condensate/water supply system that supplies water condensed by the condenser to the pressure vessel; and a power system that derives the gas components in the condenser and selectively removes the hydrogen contained therein. A nuclear power plant comprising: an auxiliary power system equipped with a hydrogen recovery device composed of a permeable membrane; wherein a conduit for hydrogen recovered by the hydrogen recovery device is connected to the condensate/water supply system; It is characterized by the presence of
以下、添付した図面に即して本発明の原子力プ
ラントの一実施態様を詳細に説明する。 EMBODIMENT OF THE INVENTION Hereinafter, one embodiment of the nuclear power plant of the present invention will be described in detail with reference to the attached drawings.
第１図は、本発明の原子力プラントの構成の一
例を示した概略系統図である。 FIG. 1 is a schematic system diagram showing an example of the configuration of a nuclear power plant according to the present invention.
第２図は、本発明に係る水素回収装置の構成の
一例を示した模式図である。 FIG. 2 is a schematic diagram showing an example of the configuration of a hydrogen recovery apparatus according to the present invention.
第１図の実施例は、沸騰水形原子炉の圧力容器
１に一端を接続する主蒸気管２と、該主蒸気管２
の他端に接続され、主蒸気管２を介して前記圧力
容器１から供給される蒸気によつて駆動するター
ビン３と、該タービン３に連結して回転する発電
機４と、前記タービン３の下流部に設けられ、タ
ービン３からの排蒸気を凝縮する復水器５と、復
水ポンプ６，復水浄化装置７，給水加熱器８，及
び給水ポンプ９から構成さ、前記復水器により凝
縮された水を記圧力容器１に循環せしめる復水・
給水系統１０から成る動力系；
前記復水器５からガス成分を導出する空気抽出
器１１，該抽出器１１に接続され前記ガス成分に
含まれる水素と酸素とを結合させる再結合器１
２，及び該再結合器１２により生成した水蒸気を
凝縮する排ガス復水器１３を具備する副動力系；
を備えている。 The embodiment shown in FIG. 1 includes a main steam pipe 2 whose one end is connected to a pressure vessel 1 of a boiling water reactor, and
A turbine 3 connected to the other end and driven by steam supplied from the pressure vessel 1 via the main steam pipe 2; a generator 4 connected to the turbine 3 and rotating; Consisting of a condenser 5 installed downstream and condensing exhaust steam from the turbine 3, a condensate pump 6, a condensate purification device 7, a feed water heater 8, and a feed water pump 9, the condenser Condensate water that circulates condensed water to the pressure vessel 1.
A power system consisting of a water supply system 10; an air extractor 11 that extracts gas components from the condenser 5; and a recombiner 1 that is connected to the extractor 11 and combines hydrogen and oxygen contained in the gas components.
2, and an auxiliary power system comprising an exhaust gas condenser 13 that condenses the water vapor generated by the recombiner 12;
It is equipped with
前記復水・給水決統などから注入され圧力容器
内の原子炉冷却材に溶存せしめられた水素は復水
器に到達し、空気抽出器により副動力系に排出さ
れるのであるが、前記副動力系には、前記空気抽
出器により抽出されるガス成分に含有される水素
の回収装置１４が具備されており、前記空気抽出
器１１と再結合器１２との間の配管１５に接続さ
れている。第１図の例では、前記水素回収装置１
４により回収される水素の導管１６が前記復水・
給水系統１０の復水浄化装置のあとで給水加熱器
８の前の配管に接続されている。この水素回収装
置１４は、例えば大略第２図で示した様に、前記
空気抽出器により抽出されるガス成分の導入口１
７及び回収される水素の導出口１８を有する中空
容器１９の内部を区画する水素選択透過膜２０か
ら基本的に構成されており、この例では前記導入
口１７，導出口１８が夫々第１図の例において配
管１５及び導管１６に接続される。 The hydrogen injected from the condensate/water supply line and dissolved in the reactor coolant in the pressure vessel reaches the condenser and is discharged to the auxiliary power system by the air extractor. The power system is equipped with a recovery device 14 for hydrogen contained in the gas component extracted by the air extractor, and is connected to a pipe 15 between the air extractor 11 and the recombiner 12. There is. In the example of FIG. 1, the hydrogen recovery device 1
A conduit 16 for the hydrogen recovered by 4 is connected to the condensate
It is connected to the piping in front of the feed water heater 8 after the condensate purification device of the water supply system 10 . This hydrogen recovery device 14 has an inlet 1 for introducing gas components extracted by the air extractor, as roughly shown in FIG.
7 and a hydrogen selective permeable membrane 20 that partitions the inside of a hollow container 19 having an outlet 18 for hydrogen to be recovered, and in this example, the inlet 17 and the outlet 18 are respectively shown in FIG. In this example, it is connected to piping 15 and conduit 16.
前記水素選択透過膜としては、例えばパラジウ
ム、又はパラジウム−白金、パラジウム−金、パ
ラジウム−銀もしくはパラジウム−ホウ素等のパ
ラジウム基合金が挙げられる。 Examples of the hydrogen selective permeation membrane include palladium or palladium-based alloys such as palladium-platinum, palladium-gold, palladium-silver, or palladium-boron.
本発明に用いられる上記パラジウム或はパラジ
ウム基合金膜は水素を選択的に透過する能力を有
する。このことを、パラジウムを例に取り、添付
した図面に即して詳細に説明する。第３図は20〜
200℃の温度或におけるパラジウムの水素吸収等
温線を示した図であり、図中ａ〜ｇは夫々、50
℃，100℃，150℃，160℃，180℃，190℃，200℃
における水素吸収等温線である。第４図は180℃
におけるパラジウムの水素吸収ヒステリシス曲線
である。 The palladium or palladium-based alloy membrane used in the present invention has the ability to selectively permeate hydrogen. This will be explained in detail by taking palladium as an example and referring to the attached drawings. Figure 3 shows 20~
It is a diagram showing hydrogen absorption isotherms of palladium at a temperature of 200°C, and a to g in the diagram are 50°C, respectively.
℃、100℃、150℃、160℃、180℃、190℃、200℃
This is the hydrogen absorption isotherm at . Figure 4 is 180℃
This is the hydrogen absorption hysteresis curve of palladium.
パラジウム膜に水素ガスが接触すると先づ膜面
に水素濃度の高いβ相（PdH0.6）が形成され、
次いで表層から膜の内部に水素の拡散が進行し、
膜全体に亘つてβ相より水素含有量の少ないα相
（Pd2H）が形成される。更に膜面から水素が吸収
されて、α相の限界濃度を超えると表層から順次
β相が形成されて、遂には膜全体がβ相となる。 When hydrogen gas comes into contact with the palladium membrane, a β phase with high hydrogen concentration (PdH 0.6 ) is first formed on the membrane surface.
Next, hydrogen diffusion progresses from the surface layer to the inside of the membrane.
An α phase (Pd 2 H) containing less hydrogen than the β phase is formed throughout the film. Furthermore, when hydrogen is absorbed from the membrane surface and the critical concentration of the α phase is exceeded, the β phase is formed sequentially from the surface layer, and finally the entire membrane becomes the β phase.
第３図から明らかな様に、一定温度において
は、水素分圧が高い程水素吸収量が一様に高くな
るのであるが、通常水素圧力の高い前記空気抽出
器側の膜面から水素が吸収され、水素圧力の低い
復水・給水系統側の膜面の吸収能力を超える水素
が放出され、更に第４図から明らかな様に、高圧
の空気抽出器側膜面からの水素吸収及び低圧の復
水・給水系統側の膜面からの水素放出が繰返し行
なわれることとなる。 As is clear from Figure 3, at a constant temperature, the higher the hydrogen partial pressure, the higher the amount of hydrogen absorption uniformly increases, but hydrogen is normally absorbed from the membrane surface on the air extractor side, where the hydrogen pressure is high. As a result, hydrogen exceeding the absorption capacity of the membrane surface on the condensate/water supply system side where the hydrogen pressure is low is released, and as is clear from Figure 4, hydrogen is absorbed from the membrane surface on the high pressure air extractor side and Hydrogen will be released repeatedly from the membrane surface on the condensate/water supply system side.
また、第２図には図示していないが、前記水素
回収装置の空気抽出器側のトラツプ２１内もしく
は膜面２２，及び復水・給水系統側のトラップ２
３もしくは膜面２４の夫々を加熱する装置を設け
ていると、例えばトラツプ２１もしくは膜面２２
より、トラツプ２３もしくは膜面２４を高温にす
ることにより、膜２０に水素の濃度勾配が形成さ
れてこの膜による水素透過能を高めることができ
る。或は、原子炉冷却材もしくは原子炉給水中の
水素濃度を測定して膜の温度勾配にフイードバツ
クさせると、冷却材や給水中の水素濃度を微妙に
コントロールすることができる。 Although not shown in FIG. 2, there are also traps 21 or membrane surfaces 22 on the air extractor side of the hydrogen recovery device, and traps 2 on the condensate/water supply system side.
If a device is provided to heat the trap 21 or the membrane surface 24, for example, the trap 21 or the membrane surface 22 can be heated.
By increasing the temperature of the trap 23 or the membrane surface 24, a hydrogen concentration gradient is formed in the membrane 20, thereby increasing the hydrogen permeability of the membrane. Alternatively, by measuring the hydrogen concentration in the reactor coolant or reactor feed water and feeding it back to the temperature gradient of the membrane, the hydrogen concentration in the coolant or feed water can be delicately controlled.
第１図に戻ると前記圧力容器内の高圧水を循環
浄化する、再循環ポンプ２５及び炉水浄化装置２
６から成る再循環系、及び前記排ガス復水器に続
く希ガスホールドアツプ装置（第１図に図示せ
ず）などが備えられている。 Returning to FIG. 1, the recirculation pump 25 and the reactor water purification device 2 circulate and purify the high pressure water in the pressure vessel.
6 and a rare gas hold-up device (not shown in FIG. 1) following the exhaust gas condenser.
第１図の例では、前記水素回収装置１４により
回収される水素の導管１６が復水浄化装置７のあ
とで給水加熱器８の前の配管１０に接続されてい
るのであるが、本発明に係る前記導管の接続位置
はこれに限定されず、例えば復水・給水系統の他
の位置、或は再循環系などに接続されていても良
い。 In the example of FIG. 1, the hydrogen conduit 16 recovered by the hydrogen recovery device 14 is connected to the pipe 10 after the condensate purification device 7 and before the feed water heater 8. The connection position of the conduit is not limited to this, and it may be connected to, for example, another position of the condensate/water supply system, or a recirculation system.
本発明の原子力プラントによれば、原子炉構造
部材の酸化を防止する為に原子炉冷却材に注入さ
れる水素が副動力系に具備されている水素回収装
置により回収されて該冷却材中に循環再注入され
るために、注入水素が有効利用されると共に、水
素が動力系及び副動力系を介して循環されている
ために冷却材中の水素濃度が溶存酸素量に応じて
調節可能となり、従つてプラント構成部材の水素
脆化が低減される。 According to the nuclear power plant of the present invention, hydrogen injected into the reactor coolant in order to prevent oxidation of the reactor structural members is recovered by the hydrogen recovery device provided in the auxiliary power system and added to the coolant. Since the hydrogen is recycled and re-injected, the injected hydrogen is effectively used, and since the hydrogen is circulated through the power system and auxiliary power system, the hydrogen concentration in the coolant can be adjusted according to the amount of dissolved oxygen. , thus reducing hydrogen embrittlement of plant components.
第１図は、本発明の原子力プラントの構成の一
例を示した概略系統図である。第２図は、本発明
に系る水素回収装置の構成の一例を示した模式図
である。第３図及び第４図は本発明に用いられる
パラジウムの水素吸収性能を示した曲線図であ
り、第３図は20〜200℃における水素吸収等温曲
線図、第４図は180℃における水素吸収ヒステリ
シス曲線図である。
１……圧力容器、２……主蒸気管、３……ター
ビン、４……発電機、５……復水器、６……復水
ポンプ、７……復水浄化装置、８……給水加熱
器、９……給水ポンプ、１０……配管、１１……
空気抽出器、１２……再結合器、１３……排ガス
復水器、１４……水素回収装置、１５……配管、
１６……導管、１７……導入口、１８……導出
口、１９……中空容器、２０……水素選択透過
膜、２１，２３……トラツプ、２２，２４……膜
面、２５……再循環ポンプ、２６……炉水浄化装
置。
FIG. 1 is a schematic system diagram showing an example of the configuration of a nuclear power plant according to the present invention. FIG. 2 is a schematic diagram showing an example of the configuration of a hydrogen recovery apparatus according to the present invention. Figures 3 and 4 are curve diagrams showing the hydrogen absorption performance of palladium used in the present invention. Figure 3 is a hydrogen absorption isothermal curve diagram at 20 to 200 °C, and Figure 4 is a hydrogen absorption isotherm diagram at 180 °C. It is a hysteresis curve diagram. 1... Pressure vessel, 2... Main steam pipe, 3... Turbine, 4... Generator, 5... Condenser, 6... Condensate pump, 7... Condensate purification device, 8... Water supply Heater, 9...Water pump, 10...Piping, 11...
Air extractor, 12... Recombiner, 13... Exhaust gas condenser, 14... Hydrogen recovery device, 15... Piping,
16... Conduit, 17... Inlet, 18... Outlet, 19... Hollow container, 20... Hydrogen selective permeation membrane, 21, 23... Trap, 22, 24... Membrane surface, 25... Re- Circulation pump, 26...Reactor water purification device.
Claims (1)
主蒸気管と、該主蒸気管の他端に接続されるター
ビンと、該タービンに続く復水器と、該復水器に
より凝縮される水を前記の圧力容器に供給する復
水・給水系統から成る動力系；及び、 前記の復水器内のガス成分を導出し、含有され
る水素を選択的に透過する膜から構成される水素
回収装置を具備する副動力系； を備えている原子力プラントであつて、 前記の水素回収装置により回収される水素の導
管が前記の復水・給水系統に接続されていること
を特徴とする原子力プラント。[Scope of Claims] 1. A main steam pipe connected at one end to a pressure vessel of a boiling water reactor, a turbine connected to the other end of the main steam pipe, a condenser following the turbine, and a condenser connected to the other end of the main steam pipe. A power system consisting of a condensate/water supply system that supplies water condensed by the water condenser to the pressure vessel; and a gas component in the condenser and selectively permeates the hydrogen contained therein. A nuclear power plant comprising: an auxiliary power system equipped with a hydrogen recovery device composed of a membrane; a conduit for hydrogen recovered by the hydrogen recovery device is connected to the condensate/water supply system; A nuclear power plant characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56042512A JPS57157197A (en) | 1981-03-25 | 1981-03-25 | Atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56042512A JPS57157197A (en) | 1981-03-25 | 1981-03-25 | Atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57157197A JPS57157197A (en) | 1982-09-28 |
| JPH027440B2 true JPH027440B2 (en) | 1990-02-19 |
Family
ID=12638115
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56042512A Granted JPS57157197A (en) | 1981-03-25 | 1981-03-25 | Atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57157197A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59220687A (en) * | 1983-05-30 | 1984-12-12 | 株式会社日立製作所 | Method of controlling corrosion environment in reactor primary coolant circuit |
-
1981
- 1981-03-25 JP JP56042512A patent/JPS57157197A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57157197A (en) | 1982-09-28 |
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