JPS637639B2 - - Google Patents
Info
- Publication number
- JPS637639B2 JPS637639B2 JP55133554A JP13355480A JPS637639B2 JP S637639 B2 JPS637639 B2 JP S637639B2 JP 55133554 A JP55133554 A JP 55133554A JP 13355480 A JP13355480 A JP 13355480A JP S637639 B2 JPS637639 B2 JP S637639B2
- Authority
- JP
- Japan
- Prior art keywords
- control
- flow rate
- control rod
- recirculation
- recirculation flow
- 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
- 230000007423 decrease Effects 0.000 claims description 7
- 230000037431 insertion Effects 0.000 claims description 6
- 238000003780 insertion Methods 0.000 claims description 6
- 230000002265 prevention Effects 0.000 description 9
- 230000001174 ascending effect Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 230000003247 decreasing effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000000903 blocking effect Effects 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 230000007257 malfunction 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
-
- 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
- Safety Devices In Control Systems (AREA)
Description
【発明の詳細な説明】
この発明は例えば沸騰水型原子炉の出力制御装
置の改良に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement in a power control device for, for example, a boiling water nuclear reactor.
従来の沸騰水型原子炉の出力制御装置は、２種
類の組合せによつていた。１つは、制御棒を引抜
又は挿入することで原子炉の出力を上昇又は減少
させる制御棒制御装置である。もう１つは、原子
炉内の流量を増加又は減少することで原子炉の出
力を上昇又は減少させる再循環流量制御装置であ
る。第１図はこの種従来の原子炉出力制御装置を
示している。原子炉１の炉心部１０を流れる流量
は、Ａ系再循環ポンプ２ａとＢ系再循環ポンプ２
ｂのポンプ速度で決められる。前記再循環ポンプ
２ａ，２ｂを制御する再循環制御装置４は、Ａ系
再循環ポンプ制御部１１ａとＡ系流量増加設定部
１２ａとＡ系流量減少設定部１３ａとＢ系再循環
ポンプ制御部１１ｂとＢ系流量増加設定部１２ｂ
とＢ系流量減少設定部１３ｂとから成つている。
原子炉１に設置された制御棒２０の位置は、制御
棒駆動機構３によつて決められる。制御棒駆動機
構３は制御棒制御装置５で制御される。一方制御
パネル６には、Ａ系再循環流量増加ボタン２１、
Ａ系再循環流量減少ボタン２２とＢ系再循環流量
増加ボタン２３、Ｂ系再循環流量減少ボタン２４
と、制御棒引抜ボタン２５、制御棒挿入ボタン２
６とから成つている。 Conventional power control devices for boiling water reactors have relied on a combination of two types. One is a control rod control device that increases or decreases the power output of a nuclear reactor by withdrawing or inserting control rods. The other is a recirculation flow control device that increases or decreases the power of the reactor by increasing or decreasing the flow rate within the reactor. FIG. 1 shows a conventional reactor power control system of this type. The flow rate flowing through the core part 10 of the reactor 1 is determined by the A system recirculation pump 2a and the B system recirculation pump 2.
It is determined by the pump speed of b. The recirculation control device 4 that controls the recirculation pumps 2a and 2b includes an A-system recirculation pump control section 11a, an A-system flow rate increase setting section 12a, an A-system flow rate decrease setting section 13a, and a B-system recirculation pump control section 11b. and B system flow rate increase setting section 12b
and a B-system flow rate reduction setting section 13b.
The position of the control rods 20 installed in the nuclear reactor 1 is determined by the control rod drive mechanism 3. The control rod drive mechanism 3 is controlled by a control rod control device 5. On the other hand, the control panel 6 includes a system A recirculation flow rate increase button 21,
A system recirculation flow rate decrease button 22, B system recirculation flow rate increase button 23, B system recirculation flow rate decrease button 24
, control rod extraction button 25, control rod insertion button 2
It consists of 6.
以上のような構成の従来の原子炉出力制御装置
においては、再循環流量の制御系と制御棒の制御
系が互いに独立であるため、同時に双方の制御が
可能であつた。原子炉を運転する場合、運転員は
原則として再循環流量と制御棒の同時操作は行な
わないが、もし万一この運転員が同時に出力上昇
を意図した場合は、それを禁止する物理的手段が
なく、また原子炉の出力上昇が意図した以上に上
昇することになり、運転上好ましくない。 In the conventional nuclear reactor power control device having the above configuration, the recirculation flow rate control system and the control rod control system are independent of each other, so that it is possible to control both at the same time. When operating a nuclear reactor, operators generally do not operate the recirculation flow rate and control rods at the same time, but in the unlikely event that the operator intends to increase the output at the same time, there are physical means to prevent this. Moreover, the output of the reactor will increase more than intended, which is not favorable for operation.
この発明は、出力制御がより安全で、確実に実
施できるようなインターロツクを設けることによ
り、安全性と信頼性を向上する原子炉出力制御装
置を提供することを目的とする。 An object of the present invention is to provide a nuclear reactor power control device that improves safety and reliability by providing an interlock that enables safer and more reliable power control.
以下この発明について第２図を参照して説明す
るが、ここでは第１図とは異なる部分を説明し、
第１図と同一部分は同一符号を付しその説明は省
略する。すなわち第１図の原子炉制御装置に、新
たに制御棒インターロツク装置７と、再循環イン
ターロツク装置８を設け、さらに再循環流量制御
装置４のＡ系流量増加設定部１２ａにＡ系流量増
加阻止部１４ａを設け、Ｂ系流量増加設定部１２
ｂにＢ系流量増加阻止部１４ｂを設け、さらにま
た制御棒制御装置５に制御棒引抜阻止部１５を設
けてある。 This invention will be explained below with reference to FIG. 2, but here, parts different from FIG. 1 will be explained,
Components that are the same as those in FIG. 1 are designated by the same reference numerals, and their description will be omitted. That is, a control rod interlock device 7 and a recirculation interlock device 8 are newly installed in the reactor control system shown in FIG. A blocking section 14a is provided, and a B system flow rate increase setting section 12 is provided.
b is provided with a B system flow rate increase prevention section 14b, and the control rod control device 5 is further provided with a control rod withdrawal prevention section 15.
このような構成のものにおいて、制御パネル６
に設置されているＡ系再循環流量増加ボタン２１
を押すことによりＡ系流量増加設定部１２ａから
プラス方向の信号が発生し前記Ａ系再循環ポンプ
制御部１１ａに入力され、ポンプスピード要求信
号が前記Ａ系再循環ポンプ制御部１１ａからＡ系
再循環ポンプ２ａに出力される。また前記制御パ
ネル６に設置されているＡ系再循環流量減少ボタ
ン２２を押すとＡ系流量減少設定部１３ａからマ
イナス方向の信号が発生し前記Ａ系再循環ポンプ
制御部１１ａに入力され、ポンプスピード要求信
号が前記Ａ系再循環ポンプ制御部１１ａからＡ系
再循環ポンプ２ａに出力される。この時前記Ａ系
再循環ポンプ制御部１１ａの出力であるポンプス
ピード要求信号は同時に制御棒インターロツク装
置７へも出力される。Ｂ系再循環ポンプ制御につ
いても同様である。制御棒インターロツク７は、
前記Ａ系及びＢ系のポンプスピード要求信号が上
昇方向にあるか下降方向にあるかを判定し、もし
上昇方向であるならば制御棒引抜阻止信号が制御
棒制御装置５の制御棒引抜阻止部１５に出力され
る。一方制御パネル６に設置されている制御棒引
抜ボタン２５を押すことにより、制御棒引抜阻止
部１５が動作していなければ、制御棒制御装置５
から制御棒駆動機構３へ制御棒引抜操作信号が出
力される。また前記制御パネル６に設置されてい
る制御棒挿入ボタン２６を押すことにより、前記
制御棒制御装置５から前記制御棒駆動機構３へ制
御棒挿入操作信号が出力される。この時前記制御
棒制御装置５の出力である制御棒引抜又は挿入操
作信号は、同時に再循環インターロツク置装８へ
も出力される。再循環インターロツク装置８は、
制御棒が挿入方向であるか引抜方向であるかを判
定し、引抜方向であるならば、再循環流量増加阻
止信号がＡ系流量増加設定部１２ａのＡ系流量増
加阻止部１４ａへ出力されると同時にＢ系流量増
加阻止部１４ｂへも出力される。Ａ系流量増加阻
止部１４ａが動作すると、制御パネル６に設置さ
れているＡ系再循環流量増加ボタン２１が押され
ても、Ａ系流量増加設定部１２ｄからはプラス方
向の信号は発生しない。Ｂ系についても同様であ
る。 In such a configuration, the control panel 6
A system recirculation flow rate increase button 21 installed in
By pressing , a positive signal is generated from the A-system flow increase setting section 12a and input to the A-system recirculation pump control section 11a, and a pump speed request signal is sent from the A-system recirculation pump control section 11a to the A-system recirculation pump control section 11a. It is output to the circulation pump 2a. Further, when the A-system recirculation flow rate reduction button 22 installed on the control panel 6 is pressed, a negative signal is generated from the A-system flow rate reduction setting section 13a, which is input to the A-system recirculation pump control section 11a, and the pump A speed request signal is output from the A-system recirculation pump control section 11a to the A-system recirculation pump 2a. At this time, the pump speed request signal, which is the output of the A-system recirculation pump control section 11a, is simultaneously output to the control rod interlock device 7. The same applies to the B-system recirculation pump control. Control rod interlock 7 is
It is determined whether the pump speed request signals of the A system and B system are in the ascending direction or in the descending direction, and if they are in the ascending direction, the control rod withdrawal prevention signal is sent to the control rod withdrawal prevention section of the control rod control device 5. 15. On the other hand, by pressing the control rod withdrawal button 25 installed on the control panel 6, if the control rod withdrawal prevention section 15 is not operating, the control rod control device 5
A control rod withdrawal operation signal is output from the control rod drive mechanism 3. Further, by pressing a control rod insertion button 26 installed on the control panel 6, a control rod insertion operation signal is output from the control rod control device 5 to the control rod drive mechanism 3. At this time, the control rod withdrawal or insertion operation signal output from the control rod controller 5 is simultaneously output to the recirculation interlock device 8. The recirculation interlock device 8 is
It is determined whether the control rod is in the insertion direction or the withdrawal direction, and if it is in the withdrawal direction, a recirculation flow rate increase prevention signal is output to the A-system flow rate increase prevention unit 14a of the A-system flow rate increase setting unit 12a. At the same time, it is also output to the B-system flow rate increase prevention section 14b. When the A-system flow rate increase prevention section 14a operates, even if the A-system recirculation flow rate increase button 21 installed on the control panel 6 is pressed, no positive signal is generated from the A-system flow rate increase setting section 12d. The same applies to the B series.
以上のような構成においては再循環流量を増加
させる場合は制御棒引抜が阻止され、逆に制御棒
を引抜いている場合は再循環流量の増加が阻止さ
れるため、原子炉の出力上昇は、制御棒と再循環
流量との同時制御が不可能となり、必ずどちらか
一方のみで実施される。一方出力下降の場合は、
従来どうり同時に実施できる。 In the above configuration, control rod withdrawal is prevented when the recirculation flow rate is increased, and conversely, when the control rods are withdrawn, an increase in the recirculation flow rate is prevented, so the increase in reactor output is Simultaneous control of control rods and recirculation flow rate becomes impossible, and only one or the other is required. On the other hand, if the output decreases,
They can be performed simultaneously as before.
以上述べたこの発明によれば、原子炉の出力上
昇時における誤操作を防止できる他、さらに今後
原子力発電所の自動化が進むにつれて、再循環流
量制御と制御棒制御が、一方が自動で他方が手動
という場合が発生しても、誤操作、誤動作が阻止
できる。一方出力下降方向に対しては、何らの制
限も加えないため、原子炉の停止操作に対して
は、少しの外乱も与えない。以上により、この発
明装置を使用するならば、原子力発電所の稼動率
及び信頼性の向上が計れる他、安全性もきわめて
高くなる。 According to the invention described above, it is possible to prevent erroneous operation when the output of a nuclear reactor increases, and as nuclear power plants become more automated in the future, recirculation flow rate control and control rod control can be controlled so that one is automatic and the other is manual. Even if such a situation occurs, erroneous operations and malfunctions can be prevented. On the other hand, since no restrictions are placed on the power decreasing direction, no disturbance is caused to the nuclear reactor shutdown operation. As described above, if the device of this invention is used, the operating rate and reliability of a nuclear power plant can be improved, and safety can also be extremely improved.
第１図は従来の原子炉出力制御装置の一例を示
すブロツク図、第２図はこの発明の原子炉出力制
御装置の一実施例を示すブロツク図である。
１…原子炉、２…再循環ポンプ、３…制御棒駆
動機構、４…再循環制御装置、５…制御棒制御装
置、６…制御パネル、７…制御棒インターロツク
装置、８…再循環インターロツク装置。
FIG. 1 is a block diagram showing an example of a conventional nuclear reactor power control device, and FIG. 2 is a block diagram showing an embodiment of the nuclear reactor power control device of the present invention. DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 2... Recirculation pump, 3... Control rod drive mechanism, 4... Recirculation control device, 5... Control rod control device, 6... Control panel, 7... Control rod interlock device, 8... Recirculation interlock Locking device.
Claims (1)
御装置と、原子炉内の制御棒位置を制御する制御
棒制御装置と、前記再循環流量制御装置から出力
される流量要求信号の増減を判定し、制御棒引抜
を阻止する制御棒インターロツク装置と、前記制
御棒制御装置から出力される制御棒引抜・挿入信
号を判定し、再循環流量設定の増加を阻止する再
循環流量インターロツク装置とから成り、再循環
流量の増加と、制御棒引抜が同時に発生しないこ
とを特徴とする原子炉出力制御装置。1. A recirculation flow rate control device that controls the recirculation flow rate of the reactor, a control rod control device that controls the position of control rods in the reactor, and determining an increase or decrease in the flow rate request signal output from the recirculation flow rate control device. a control rod interlock device that prevents control rod withdrawal, and a recirculation flow rate interlock device that determines a control rod withdrawal/insertion signal output from the control rod control device and prevents an increase in the recirculation flow rate setting. A nuclear reactor power control device comprising: an increase in recirculation flow rate and a control rod withdrawal that do not occur at the same time.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55133554A JPS5757283A (en) | 1980-09-25 | 1980-09-25 | Nuclear reactor power control device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55133554A JPS5757283A (en) | 1980-09-25 | 1980-09-25 | Nuclear reactor power control device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5757283A JPS5757283A (en) | 1982-04-06 |
| JPS637639B2 true JPS637639B2 (en) | 1988-02-17 |
Family
ID=15107520
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55133554A Granted JPS5757283A (en) | 1980-09-25 | 1980-09-25 | Nuclear reactor power control device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5757283A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0269828U (en) * | 1988-11-15 | 1990-05-28 |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59134529U (en) * | 1983-02-28 | 1984-09-08 | オ−ツタイヤ株式会社 | Agricultural wheel manufacturing equipment |
-
1980
- 1980-09-25 JP JP55133554A patent/JPS5757283A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0269828U (en) * | 1988-11-15 | 1990-05-28 |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5757283A (en) | 1982-04-06 |
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