JPS5928802B2 - Nuclear plant steam temperature control device - Google Patents
Nuclear plant steam temperature control deviceInfo
- Publication number
- JPS5928802B2 JPS5928802B2 JP51051864A JP5186476A JPS5928802B2 JP S5928802 B2 JPS5928802 B2 JP S5928802B2 JP 51051864 A JP51051864 A JP 51051864A JP 5186476 A JP5186476 A JP 5186476A JP S5928802 B2 JPS5928802 B2 JP S5928802B2
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- steam
- control device
- evaporator
- circulation system
- 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 23
- 238000011144 upstream manufacturing Methods 0.000 claims description 2
- 239000011734 sodium Substances 0.000 description 21
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical group C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 10
- 229910052708 sodium Inorganic materials 0.000 description 10
- 239000007788 liquid Substances 0.000 description 9
- 230000001105 regulatory effect Effects 0.000 description 5
- 230000003247 decreasing effect Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 229920006395 saturated elastomer Polymers 0.000 description 2
- 238000004891 communication Methods 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 230000008646 thermal stress 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
- Control Of Turbines (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
Description
【発明の詳細な説明】
本発明は原子カプラントの蒸気温度特に蒸発器出口の蒸
気温度を制御する装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a device for controlling the vapor temperature of an atomic couplant, in particular the vapor temperature at the evaporator outlet.
原子カプラント例えば高速増殖炉プラントにおいて通常
負荷(30係〜100%)運転の制御方式はすでにかな
りの検討がなされ一応の方式が得られているようである
が、起動・停止(0係〜30係負荷)に対しては、はと
んど未着手の状態にあり積極的な制御を加えたものは見
かけられない。A control system for normal load (30% to 100%) operation in nuclear couplers, for example, fast breeder reactor plants, has already been extensively studied and a certain method has been developed, but for start-up and shutdown (0% to 30%) As for load), this has not been done yet, and no active control has been applied.
この理由は起動・停止時のように蒸気圧力の大幅な変化
がある場合にはその変化が沸騰の状況に多大の影響を及
ぼし不都合な結果をまねくためである。The reason for this is that if there is a large change in steam pressure, such as during startup or shutdown, that change will have a great effect on the boiling situation, leading to unfavorable results.
例えば起動時には起動時間を短かくするためにまず蒸発
器出口の蒸気を早い時機に過熱蒸気とする必要がある。For example, at startup, it is necessary to convert the steam at the evaporator outlet into superheated steam as soon as possible in order to shorten the startup time.
それには初め圧力を低い状態にして被加熱流体の飽和温
度を下げて2次ナトリウムとの温度差を大きくすること
によって入熱を増やし定格の圧力まで徐々に増圧して行
(方法が考えられるが次のような問題があって充分な効
果が得られな℃・のが現状である。To do this, first the pressure is kept low, the saturation temperature of the fluid to be heated is lowered, and the temperature difference with the secondary sodium is increased, thereby increasing the heat input and gradually increasing the pressure to the rated pressure. At present, sufficient effects cannot be obtained due to the following problems.
いま蒸発器内の圧力が上がると(一般に60〜17Oa
taの範囲にある)その圧力に対応する飽和水エンタル
ピが比例的に上昇し、最初あるエンタルピで飽和域に入
っていた蒸気が昇圧により減温し、はなはだしい場合に
は再びサブクール域に戻ってしまうという現象が生じ、
蒸発器出口以降の配管や過熱器、タービン等に腐食や熱
サイクル疲労破壊を発生させるという不具合を生ずる。Now, when the pressure inside the evaporator increases (generally 60 to 17 Oa
The enthalpy of saturated water corresponding to the pressure (in the range of ta) increases proportionally, and the steam that was initially in the saturated region at a certain enthalpy will be cooled by the increase in pressure, and in extreme cases it will return to the subcooled region again. This phenomenon occurs,
This causes problems such as corrosion and thermal cycle fatigue failure in the piping, superheater, turbine, etc. after the evaporator outlet.
又、停止時には蒸気圧力を減少させるとかえって、蒸気
発生量や蒸気温度が増大し、起動時と同様な不具合が発
生する。Furthermore, when the steam pressure is reduced when the steam generator is stopped, the amount of steam generated and the steam temperature increase, causing the same problems as when the steam generator is started.
本発明は、前記したような予想される不具合を発生させ
ずにプラントを効率よくかつ迅速に起動。The present invention enables the plant to be started efficiently and quickly without causing the above-mentioned expected problems.
停止させるためになされたものである。This was done to stop it.
すなわち本発明は、熱媒体循環系に対応して蒸発器を貫
流する蒸気循環系の前記蒸発器より上流側に流量制御器
を設け、前記蒸発器より下流側の前記蒸気循環系に圧力
設定器を含む蒸気圧力制御装置を設け、前記流量制御器
に減算器を経由して連絡する給水信号発生器を設け、前
記減算器に調整器を経由して前記圧力設定器を連絡した
原子カプラントの蒸気温度制御装置に係り、本発明によ
れば、蒸気循環系の圧力を増減する場合に蒸気圧力制御
装置の圧力設定器による圧力設定信号を流量制御系に付
加し給水流量を圧力変化に先立って調整するので、蒸気
温度を所定の値に保持しながら蒸気圧力の増減を行なう
ことができ、ひいてはプラントの起動停止を効率よくか
つ迅速に行なうことができる。That is, the present invention provides a flow rate controller on the upstream side of the evaporator in a vapor circulation system that flows through the evaporator in correspondence with the heat medium circulation system, and a pressure setting device on the vapor circulation system on the downstream side of the evaporator. a steam pressure control device comprising: a feed water signal generator communicating with the flow rate controller via a subtractor; and an atomic couplant steam signal generator communicating with the pressure setting device via a regulator with the subtractor; Regarding the temperature control device, according to the present invention, when increasing or decreasing the pressure of the steam circulation system, a pressure setting signal from the pressure setting device of the steam pressure control device is added to the flow rate control system to adjust the water supply flow rate prior to the pressure change. Therefore, the steam pressure can be increased or decreased while maintaining the steam temperature at a predetermined value, and the plant can be started and stopped efficiently and quickly.
次に本発明の実施例を図面にもとづいて説明する。Next, embodiments of the present invention will be described based on the drawings.
第1図は、本実施例の制御装置によって蒸気圧力が制御
される高速増殖炉プラントの系統図である。FIG. 1 is a system diagram of a fast breeder reactor plant whose steam pressure is controlled by the control device of this embodiment.
第1図において1は原子炉の炉心で、この炉心1には、
制御棒駆動装置2を具備する制御棒3が挿入される。In Fig. 1, 1 is the core of a nuclear reactor, and this core 1 includes:
A control rod 3 with a control rod drive 2 is inserted.
前記炉心1を流れる熱媒体すなわち液体ナトリウムの循
環系4は、中間熱交換器5および1次循環ポンプ6を通
る。A circulation system 4 of the heat medium, that is, liquid sodium, flowing through the reactor core 1 passes through an intermediate heat exchanger 5 and a primary circulation pump 6.
前記循環系4は通常1次Naループ4と呼ばれる。The circulatory system 4 is usually called the primary Na loop 4.
同1次Naループ4に対応して前記中間熱交換器5を通
る熱媒体すなわち液体ナトリウムの2次循環系すなわち
2次Naループ7は、過熱器8と再熱器9とを分れて通
り、合流後蓋発器10と2次循環ポンプ11とを順次通
り前記中間熱交換器5に帰環する。A secondary circulation system, that is, a secondary Na loop 7 for the heat medium, that is, liquid sodium, which passes through the intermediate heat exchanger 5 in correspondence with the primary Na loop 4, passes through the superheater 8 and the reheater 9 separately. After merging, the heat is returned to the intermediate heat exchanger 5 through the lid generator 10 and the secondary circulation pump 11 in sequence.
給水ポンプ12を出て給水制御弁13を通り、前記2次
Naループ7に対応して蒸発器10および過熱器8を順
次通り、更に調速弁14を通って高圧タービン15に至
り、同高圧タービン15を出て再熱器9を通り低圧ター
ビンに至った後前記給水ポンプ13′に帰環する蒸気循
環系16が設げられている。It exits the feed water pump 12, passes through the feed water control valve 13, passes through the evaporator 10 and superheater 8 in sequence corresponding to the secondary Na loop 7, further passes through the speed regulating valve 14, reaches the high pressure turbine 15, and the high pressure A steam circulation system 16 is provided which exits the turbine 15, passes through the reheater 9, reaches the low pressure turbine, and then returns to the feed water pump 13'.
第2図は本実施例の制御装置の系統を示したもので、第
2図において蒸発器10より出る蒸気循環系16に設げ
られた温度検出器17、比較器18を介して蒸発器出口
温度設定器19に連絡し、同比較器18は比例積分動作
調節器20を介して加算器21に連絡し、これら温度検
出器17、比較器18、蒸発器出口温度設定器19、比
例積分動作調節器20および加算器21はいわゆる補償
回路を形成している。FIG. 2 shows the system of the control device of this embodiment. In FIG. The comparator 18 communicates with the adder 21 via the proportional-integral operation regulator 20, and the temperature detector 17, the comparator 18, the evaporator outlet temperature setter 19, the proportional-integral operation Regulator 20 and adder 21 form a so-called compensation circuit.
図示しない中央制御装置に関して設けられた給水信号発
生器22は、減算器23、および加算器21を介して制
御器すなわち回転数調節器24に電気的に連絡し、前記
回転数調節器24は給水ポンプ12に付設されている。A water supply signal generator 22, which is provided with respect to a central control unit (not shown), is electrically connected via a subtractor 23 and an adder 21 to a controller or rotational speed regulator 24, said rotational speed regulator 24 It is attached to the pump 12.
前記調速弁14に関して蒸気循環系16に設げられた圧
力検出器25は比較器26を介して、比例積分動作調節
器27と圧力設定器28とに電気的に連絡し、前記比例
積分動作調節器27は前記調速弁14に連絡している。A pressure detector 25 provided in the steam circulation system 16 with respect to the regulating valve 14 is electrically connected to a proportional-integral operation regulator 27 and a pressure setting device 28 via a comparator 26, and The regulator 27 is in communication with the speed regulating valve 14 .
これら調速弁14、圧力検出器25、比較器26、比例
積分動作調節器27および圧力設定器28は一体となっ
て蒸気圧力制御装置29を形成すると共に前記圧力設定
器28は調節器すなわち比例微分動作調節器30を介し
て前記減算器23に電気的に連絡□している。The regulating valve 14, the pressure detector 25, the comparator 26, the proportional-integral operation regulator 27, and the pressure setting device 28 together form a steam pressure control device 29, and the pressure setting device 28 is a regulator, that is, a proportional It is electrically connected to the subtractor 23 via a differential operation regulator 30.
まず前記した構成の本実施例が適用されたプラント(第
1図)の通常運転について説明すると炉心1で発生した
核反応熱は1次Naループ4を流れる液体ナトリウムに
伝えられ、受熱して昇温しだ液体ナトリウムは中間熱交
換器5に流入し、ここで2次Naループ7を流れる液体
ナトリウムに授熱し、それ自体は減温して低温となり1
次循環ポンプ6を通って再び炉心1に戻り、運転中はこ
のサイクルを繰返す。First, to explain the normal operation of the plant (Fig. 1) to which this embodiment of the above-described configuration is applied, the nuclear reaction heat generated in the reactor core 1 is transferred to the liquid sodium flowing through the primary Na loop 4, which receives heat and rises. The warmed liquid sodium flows into the intermediate heat exchanger 5, where it transfers heat to the liquid sodium flowing through the secondary Na loop 7, and the temperature of the liquid sodium itself decreases to 1.
It passes through the next circulation pump 6 and returns to the core 1, and this cycle is repeated during operation.
前記したように中間熱交換器5で受熱し高温となった2
次Naループ7の液体ナトリウムは、過熱器8および再
熱器9を流れて蒸気循環系16の蒸気に授熱し、更に蒸
発器10に入って蒸気循環系16を流れて蒸発器10に
入る給水に授熱し従って前記給水は沸騰蒸発し蒸気とな
る。As mentioned above, heat was received in the intermediate heat exchanger 5 and the temperature became high.
Next, the liquid sodium in the Na loop 7 flows through a superheater 8 and a reheater 9 to transfer heat to the steam in the steam circulation system 16, and further enters the evaporator 10, flows through the steam circulation system 16, and enters the feed water into the evaporator 10. Therefore, the feed water boils and evaporates into steam.
蒸発器10を出た液体ナトリウムは2次循環ポンプ11
を通り中間熱交換器5に戻り、運転中は前述したような
サイクルを繰返して2次Naループ7を循環する。The liquid sodium that has exited the evaporator 10 is sent to the secondary circulation pump 11
, and returns to the intermediate heat exchanger 5, and during operation, the above-described cycle is repeated to circulate through the secondary Na loop 7.
又前述のように蒸気循環系16はある部分では水が流れ
、ある部分では蒸気が流れる。Further, as described above, in the steam circulation system 16, water flows in some parts and steam flows in some parts.
次に前記した構成を有する本実施例の作用を起動時を例
にとって説明する。Next, the operation of this embodiment having the above-mentioned configuration will be explained by taking the startup time as an example.
制御棒1駆動装置2は図示しない通常の制御装置により
指令を受けて制御され、炉心1は所要の熱出力を発生し
ている。The control rod 1 drive device 2 is controlled by receiving a command from a normal control device (not shown), and the reactor core 1 generates a required thermal output.
1次循環ポンプ6と2次循環ポンプとは適宜作動し、前
記炉心1の熱出力に見合う量の液体ナトリウムをそれぞ
れ1次Naループ4および2次Naループ7に循環させ
ている。The primary circulation pump 6 and the secondary circulation pump operate appropriately to circulate liquid sodium in an amount corresponding to the thermal output of the reactor core 1 to the primary Na loop 4 and the secondary Na loop 7, respectively.
これに対し給水ポンプ12は給水信号発生器22の基準
給水信号を受けて回転制御され所定の給水を蒸発器10
に供給し規定の特性に達しない蒸気(又は水)は蒸気循
環系16に設けられた図示しない排出系から外部に逃が
している。On the other hand, the water supply pump 12 receives a reference water supply signal from the water supply signal generator 22 and is controlled to rotate, and supplies predetermined water to the evaporator 10.
Steam (or water) that is supplied to the steam circulation system 16 and does not reach specified characteristics is discharged to the outside through a discharge system (not shown) provided in the steam circulation system 16.
蒸気循環系16の初期圧力は通常の方法で予め所定の圧
力(例えば60ata程度)にあげられているから、蒸
気圧力制御装置29は前記初期圧力からタービン併入圧
力を超えて所定の値まで蒸気循環系16の圧力を徐々に
一様の勾配で上昇させる。Since the initial pressure of the steam circulation system 16 is raised to a predetermined pressure (for example, about 60 ata) in advance by a normal method, the steam pressure control device 29 controls the steam pressure from the initial pressure to a predetermined value exceeding the turbine input pressure. The pressure in the circulation system 16 is gradually increased with a uniform gradient.
この変化する設定圧力は圧力設定器28から時間の関数
として出力され、比較器26で圧力検出器25による検
出圧力と比較されて圧力偏差が出力される。This changing set pressure is output from the pressure setting device 28 as a function of time, and is compared with the pressure detected by the pressure detector 25 by the comparator 26, and a pressure deviation is output.
同圧力偏差は比例積分動作調節器27に入力し処理され
てその出力により調速弁14の弁開度が調整され蒸気循
環系16の圧力は前記設定圧力に従って上昇する。The pressure deviation is input to the proportional-integral operation regulator 27 and processed, and the valve opening of the speed regulating valve 14 is adjusted by the output thereof, and the pressure of the steam circulation system 16 is increased in accordance with the set pressure.
この蒸気圧力制御装置29の作用と同時に前記設定圧力
は比例微分動作調節器30に送られ、ここで圧力勾配に
比例する項と圧力変化に比例する項との合算の出力信号
すなわちフィードフォワード信号が発生され減算器23
に入力する。Simultaneously with the action of the steam pressure control device 29, the set pressure is sent to the proportional differential operation regulator 30, where an output signal of the sum of the term proportional to the pressure gradient and the term proportional to the pressure change, that is, a feedforward signal is generated. generated subtracter 23
Enter.
同フィードフォワード信号は前記基準信号に負に作用し
減算器23から回転数調整器24に入る入力は前記フィ
ードフォワード信号の分だけ減少し、従って給水ポンプ
12の回転数は減少し、蒸発器10に供給される給水量
が減少し、従って蒸発器10における単位流量当りの受
熱量は増大する。The feedforward signal has a negative effect on the reference signal, and the input from the subtractor 23 to the rotation speed regulator 24 is reduced by the amount of the feedforward signal, so that the rotation speed of the water pump 12 is reduced and the evaporator 10 The amount of water supplied to the evaporator 10 decreases, and therefore the amount of heat received per unit flow rate in the evaporator 10 increases.
前記蒸気圧力制御装置29の作用による昇圧により蒸発
器10内で沸騰領域の変化はおきるが、前記比例微分動
作調節器30の作用により予め、かつ昇圧作用中給水流
量が減少されているので蒸気循環系16の蒸発器10の
出口温度は所定の値に保持される。Although a change in the boiling region occurs in the evaporator 10 due to the pressure increase caused by the action of the steam pressure control device 29, the flow rate of feed water is reduced in advance and during the pressure increase action by the action of the proportional differential operation regulator 30, so that steam circulation is prevented. The outlet temperature of the evaporator 10 of the system 16 is maintained at a predetermined value.
温度検出器17等を含む補償回路は、前記所定の値の設
定温度を出力する蒸発器出口温度設定器19の作用によ
り補償信号を加算器21に付加し前述のフィードフォワ
ード信号による作用を補完する。The compensation circuit including the temperature detector 17 etc. adds a compensation signal to the adder 21 by the action of the evaporator outlet temperature setter 19 which outputs the set temperature of the predetermined value, and complements the action by the feedforward signal described above. .
なお前述の設定圧力は一様勾配の上昇圧力としたが、他
のパターン例えば階段状に上昇する変化圧力としてもよ
いことは勿論であり、又前記基準給水信号は一定に保持
しなくても徐々に増加させることも考えられる。Although the above-mentioned set pressure is a rising pressure with a uniform gradient, it is of course possible to use other patterns, such as a variable pressure that rises stepwise, and the reference water supply signal does not need to be held constant but may be set gradually. It is also conceivable to increase it to
前述したように本実施例によれば蒸気圧力制御装置29
の圧力設定器28の設定圧力を比例微分することにより
蒸気循環系16の昇圧に先立ちかつ並行して給水流量を
減少するので昇圧による温度降下を防止しえ、ひいては
蒸気循環系16の配管、過熱器9およびタービン等に過
大な熱応力や腐食等を発生することなく、プラントを効
率よく迅速に起動することができる。As mentioned above, according to this embodiment, the steam pressure control device 29
By proportionally differentiating the set pressure of the pressure setting device 28, the water supply flow rate is reduced prior to and in parallel with the pressure increase in the steam circulation system 16, thereby preventing a temperature drop due to pressure increase, and thus preventing the piping of the steam circulation system 16 from overheating. The plant can be started efficiently and quickly without causing excessive thermal stress, corrosion, etc. to the vessel 9, turbine, etc.
以上本実施例による起動時の蒸発器出口温度の制御作用
を詳述したが、停機時は起動時とは逆に圧力設定器28
の設定圧力として一様に減少する圧力を使用すれば所期
の目的が達成されることは当業者なら容易に理解できる
であろう。The control action of the evaporator outlet temperature at the time of startup according to this embodiment has been described in detail above, but at the time of shutdown, the pressure setting device 28
Those skilled in the art will readily understand that using a uniformly decreasing pressure as the set pressure will achieve the desired objective.
第1図は本発明の実施例が適用されたプラントの系統図
、第2図は本発明の実施例を示す系統図である。
1・・・炉心、7・・・2次Naループ、10・・・蒸
発器、12・・・給水ポンプ、14・・・調速弁、16
・・・蒸気循環系、21・・・加算器、22・・・給水
信号発生器、23・・・減算器、24・・・回転数調整
器、25・・・圧力検出器、26・・・比較器、27・
・・比例積分動作調整器、28・・・圧力設定器、29
・・・蒸気圧力制御装置、30・・・比例微分動作調節
器。FIG. 1 is a system diagram of a plant to which an embodiment of the present invention is applied, and FIG. 2 is a system diagram showing an embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Core, 7... Secondary Na loop, 10... Evaporator, 12... Water supply pump, 14... Governor valve, 16
... Steam circulation system, 21 ... Adder, 22 ... Water supply signal generator, 23 ... Subtractor, 24 ... Rotation speed regulator, 25 ... Pressure detector, 26 ...・Comparator, 27・
...Proportional-integral action regulator, 28...Pressure setting device, 29
... Steam pressure control device, 30 ... Proportional differential operation regulator.
Claims (1)
系の前記蒸発器より上流側に流量制御器を設け、前記蒸
発器より下流側の前記蒸気循環系に圧力設定器を含む蒸
気圧力制御装置を設け、前記流量制御器に減算器を経由
して連絡する給水信号発生器を設け、前記減算器に調整
器を経由して前記圧力設定器を連絡したことを特徴とす
る原子カプラントの蒸気温度制御装置。1 A flow rate controller is provided upstream of the evaporator in a steam circulation system that flows through the evaporator in correspondence with the heat medium circulation system, and a steam pressure control device is provided in the steam circulation system downstream of the evaporator, including a pressure setting device. An atomic coupler comprising a control device, a water supply signal generator communicating with the flow rate controller via a subtracter, and communicating the pressure setting device with the subtractor via a regulator. Steam temperature control device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP51051864A JPS5928802B2 (en) | 1976-05-07 | 1976-05-07 | Nuclear plant steam temperature control device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP51051864A JPS5928802B2 (en) | 1976-05-07 | 1976-05-07 | Nuclear plant steam temperature control device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS52134995A JPS52134995A (en) | 1977-11-11 |
| JPS5928802B2 true JPS5928802B2 (en) | 1984-07-16 |
Family
ID=12898725
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP51051864A Expired JPS5928802B2 (en) | 1976-05-07 | 1976-05-07 | Nuclear plant steam temperature control device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5928802B2 (en) |
-
1976
- 1976-05-07 JP JP51051864A patent/JPS5928802B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS52134995A (en) | 1977-11-11 |
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