JPH0245160B2 - - Google Patents
Info
- Publication number
- JPH0245160B2 JPH0245160B2 JP56011969A JP1196981A JPH0245160B2 JP H0245160 B2 JPH0245160 B2 JP H0245160B2 JP 56011969 A JP56011969 A JP 56011969A JP 1196981 A JP1196981 A JP 1196981A JP H0245160 B2 JPH0245160 B2 JP H0245160B2
- Authority
- JP
- Japan
- Prior art keywords
- output
- fluctuation
- power
- reactor
- range
- 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
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、原子力発電所の原子炉出力調整装置
に係り、特に、短期間に変動する負荷変動要求を
実現することのできる原子炉出力調整装置に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor power adjustment device for a nuclear power plant, and particularly to a reactor power adjustment device that can realize load fluctuation requests that fluctuate in a short period of time.
従来、原子力発電所においては、発電用電源設
備に占める原子力発電の占有率がそれほど大きく
ないこと、発電原価が火力のそれに比較して安い
こと、負荷変動要求にそつた運転を行なつた実績
のないこと、炉心熱出力の増減に伴なう核燃料の
健全性を確実に維持することが困難である等の
種々の理由により基底負荷運転が採用されてい
る。 Conventionally, at nuclear power plants, the share of nuclear power generation in the power supply equipment for power generation is not so large, the cost of power generation is lower than that of thermal power, and there is a track record of operation that meets load fluctuation requirements. Base load operation has been adopted for a variety of reasons, including the lack of fuel efficiency and the difficulty of reliably maintaining the integrity of the nuclear fuel as the core thermal output increases and decreases.
このため、従来火力発電所や水力発電所の出力
を変化することにより、日負荷や週負荷のような
負荷の変動に対応している。 For this reason, conventionally, by changing the output of thermal power plants and hydroelectric power plants, changes in load, such as daily load or weekly load, have been responded to.
しかしながら、近年、我が国においては、原子
力発電所の増加および単機容量の大型化により、
総発電電力量に占める原子力発電の比率が大巾に
増大して来ており、短期間、例えば数分の値で変
化する出力変動要求に対応することのできる原子
力発電所が要望されている。 However, in recent years in Japan, due to the increase in the number of nuclear power plants and the increase in single unit capacity,
The proportion of nuclear power generation in the total amount of power generated has been increasing significantly, and there is a need for nuclear power plants that can respond to output fluctuation demands that change over a short period of time, for example, within a few minutes.
しかしながら、一般に、原子炉、例えば沸騰水
形原子炉においては、燃料や炉心等の原子炉の健
全性を保ちながら、負荷変動を実現する必要があ
り、従来、このような短期間に変化する出力変動
要求に対応することは、要求される出力変動に対
して、原子炉の健全性が保たれるかどうかを迅速
に監視することができないため、困難であつた。 However, in general, in nuclear reactors, such as boiling water reactors, it is necessary to realize load fluctuations while maintaining the integrity of the reactor, such as the fuel and reactor core. Responding to fluctuating demands has been difficult because it is not possible to quickly monitor whether the reactor's health is maintained in response to the required power fluctuations.
本発明は、かかる従来の事情に対処してなされ
たもので、炉心状態の健全性を保持可能な出力変
動の許容範囲を計算する出力変動幅決定装置と、
要求される出力変動の値が前記許容範囲内にある
か否かを判断し、許容範囲内にある場合には、前
記要求される出力変動の値を、そのまま出力変動
値として出力し、許容範囲外となる場合には、許
容範囲の限界値を出力変動値として出力するリミ
ツタと、前記出力変動値を入力し、この出力変動
値に基づいて、原子炉の出力変動を行なう出力変
更装置とを備えたことを特徴とする原子炉出力調
整装置を提供しようとするものである。 The present invention has been made in response to such conventional circumstances, and includes a power fluctuation range determination device that calculates an allowable range of power fluctuation that can maintain the health of the core state.
It is determined whether the required output fluctuation value is within the permissible range, and if it is within the permissible range, the required output fluctuation value is output as is as an output fluctuation value, and the permissible range is determined. If it is outside the range, a limiter outputs the limit value of the allowable range as an output fluctuation value, and an output change device inputs the output fluctuation value and changes the output of the reactor based on this output fluctuation value. It is an object of the present invention to provide a nuclear reactor power adjustment device characterized by the following features.
以下本発明の詳細を図面に示す一実施例につい
て説明する。 DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The details of the present invention will be described below with reference to an embodiment shown in the drawings.
図に示す原子炉出力調整装置は、原子炉状態量
入力装置1、プロセス計算機2、出力変動幅決定
装置3、リミツタ4および出力自動変更装置5と
から構成されている。 The reactor power adjustment device shown in the figure is composed of a reactor state quantity input device 1, a process computer 2, an output fluctuation range determination device 3, a limiter 4, and an automatic output change device 5.
原子炉状態量入力装置1は、例えば沸騰水形の
原子炉6から、炉心流量、中性子束、制御棒パタ
ーン等の原子炉の状態を示す種々の状態量を入力
する。 The reactor state quantity input device 1 inputs various state quantities indicating the state of the reactor, such as core flow rate, neutron flux, and control rod pattern, from a boiling water reactor 6, for example.
プロセス計算機2は、原子炉状態量入力装置1
から原子炉の状態を示す種々の状態量を入力し、
炉心内三次元出力分布を計算するとともに、計算
された炉心内三次元出力分布に基づいて炉心状態
を監視する。 The process computer 2 is a reactor state quantity input device 1
Input various state quantities indicating the state of the reactor from
The three-dimensional power distribution within the core is calculated, and the core status is monitored based on the calculated three-dimensional power distribution within the core.
なお、この実施例においては、炉心内三次元出
力分布の計算周期は1時間である。 In this example, the calculation cycle of the three-dimensional power distribution within the core is one hour.
出力変動幅決定装置3は、炉心状態の健全性を
保つために必要とされる炉心流量変動を伴なつた
出力変動の上限値と下限値とを計算する。 The power fluctuation width determining device 3 calculates the upper limit and lower limit of the power fluctuation accompanied by the core flow rate fluctuation required to maintain the health of the core state.
一般に、沸騰水形の原子炉6では、炉心状態の
健全性を保つために、PCエンベローブと呼ばれ
る燃料ピンの線出力密度の制限、燃料集合体の出
力を膜沸騰が生ずる限界出力との比である限界出
力比の制限、炉心流量の上・下限値の制限、いわ
ゆるロツドブロツクラインにより規制される炉心
流量と出力との制限等種々の制限が設けられてお
り、原子炉6は、これらの制限値を越えない範囲
で運転される必要がある。 In general, in a boiling water reactor 6, in order to maintain the health of the reactor core, the linear power density of the fuel pins called the PC envelope is limited, and the output of the fuel assembly is set as a ratio to the critical output at which film boiling occurs. There are various restrictions such as a certain limit power ratio restriction, upper and lower limits of the core flow rate, and restrictions on the core flow rate and output regulated by the so-called rod block line. It is necessary to operate within a range that does not exceed the limit value.
すなわち、出力変動幅決定装置3は、プロセス
計算機2で計算された三次元出力分布に基づい
て、炉心流量がPCエンベロープによる制限値、
限界出力比による制限値に達する流量変化量を求
めるとともに、炉心流量の上・下限値、ロツドブ
ロツクラインにより規制される炉心流量と出力と
の制限値とを考慮して、炉心流量および出力の許
容範囲を求める。 That is, the power fluctuation range determining device 3 determines whether the core flow rate is the limit value due to the PC envelope, based on the three-dimensional power distribution calculated by the process computer 2.
In addition to determining the amount of change in flow rate that reaches the limit value based on the critical power ratio, the core flow rate and power are determined by considering the upper and lower limits of the core flow rate and the limit value between the core flow rate and power regulated by the rod block line. Find the tolerance range.
なお、PCエンベロープによる制限値および限
界出力比による制限値を求めるには、三次元出力
分布を基にして、炉心流量変動による出力分布変
動を求める必要があるが、この出力変動幅決定装
置3は、プロセス計算機2で計算された三次元出
力分布を入力し、この入力された三次元出力分布
に基づいて、例えば、本出願人が先に出願した特
願昭52−142209に示すような手法により、出力レ
ベルとともに短時間に求めている。 Note that in order to obtain the limit value due to the PC envelope and the limit value due to the limit power ratio, it is necessary to determine the power distribution fluctuation due to the core flow rate fluctuation based on the three-dimensional power distribution. , the three-dimensional output distribution calculated by the process computer 2 is input, and based on this input three-dimensional output distribution, for example, by the method shown in Japanese Patent Application No. 52-142209 previously filed by the present applicant. , and the output level is required in a short period of time.
リミツタ4は、原子炉6の出力レベルを自動的
に変更する出力自動変更装置5の出力設定値とし
て入力される出力変動要求信号Aの値が、出力変
動幅決定装置3で求められた、出力変動の許容範
囲内にあるかどうかを判断し、許容範囲内にある
場合には、出力変動要求信号Aの値をそのまま、
出力変動信号として出力自動変更装置5に出力す
る。 The limiter 4 determines that the value of the output fluctuation request signal A, which is input as the output setting value of the automatic output change device 5 that automatically changes the output level of the reactor 6, is determined by the output fluctuation range determination device 3. It is determined whether the fluctuation is within the permissible range, and if it is within the permissible range, the value of the output fluctuation request signal A is changed as is.
It is output to the automatic output changing device 5 as an output fluctuation signal.
一方、許容範囲内にない場合には、許容範囲の
限界値を出力変動信号として出力自動変更装置5
に出力する。 On the other hand, if it is not within the allowable range, the output automatic change device 5 uses the limit value of the allowable range as an output fluctuation signal.
Output to.
出力自動変更装置5は、リミツタ4から出力さ
れた出力変動信号に基づいて、原子炉の出力を制
御する。 The automatic output change device 5 controls the output of the nuclear reactor based on the output fluctuation signal output from the limiter 4.
以上のように構成された原子炉出力調整装置で
は、出力変動幅決定装置3により求められた出力
の許容範囲がリミツタ4の設定値とされ、炉心状
態の健全性を損うような出力変動要求信号Aがリ
ミツタ4に入力された場合には、リミツタ4は、
この出力変動要求信号Aの値のうち、許容範囲内
にある値を出力変動信号として出力自動変更装置
5に出力するので、原子炉の健全性を保つ範囲
で、出力変動要求を最大限に実限することができ
る。 In the reactor power adjustment device configured as described above, the allowable range of power determined by the power fluctuation range determining device 3 is set as the limiter 4, and power fluctuation requests that impair the integrity of the reactor core condition are avoided. When signal A is input to limiter 4, limiter 4
Among the values of this output fluctuation request signal A, the values within the allowable range are output to the automatic output change device 5 as output fluctuation signals, so the output fluctuation request can be implemented to the maximum extent within the range that maintains the reactor health. can be limited.
以上述べたように、本発明の出力調整装置によ
れば、原子炉の健全性を保つ範囲で出力変動要求
を最大限に実限することができるとともに、短期
間、例えば、数分の値で変化する出力変動要求に
も対応することができる。 As described above, according to the power adjustment device of the present invention, it is possible to limit the output fluctuation request to the maximum extent within the range that maintains the health of the reactor, and also to reduce the power fluctuation request within a short period of time, for example, within a few minutes. It is also possible to respond to changing output fluctuation demands.
なお、実施例においては、炉心流動変動による
出力分布変動の予測計算に特願昭52−142209に示
した軸方向一次元モデルを使用したが、かならず
しもこれに限定されるものではなく、多少精度を
犠性にすれば、ポイントモデル、三次元計算モデ
ルを使用することができる。 In the example, the axial one-dimensional model shown in Japanese Patent Application No. 142209/1986 was used for the prediction calculation of power distribution fluctuations due to core flow fluctuations, but the model is not necessarily limited to this, and the accuracy may be improved to some extent. Alternatively, a point model or three-dimensional calculation model can be used.
そして、三次元計算モデルを使用するときに
は、プロセス計算機で計算された三次元出力分布
をかならずしも用いる必要はなくなるため、制御
棒操作時においても本発明を適用できるととも
に、リミツタの設定値を炉心状態に変化があつた
ときにのみ、変化させるようにすることができ
る。 When using a three-dimensional calculation model, it is no longer necessary to use the three-dimensional power distribution calculated by a process computer, so the present invention can be applied even during control rod operation, and the limiter settings can be adjusted to the core state. You can make it change only when there is a change.
図は、本発明の原子炉出力調整装置の一実施例
のブロツク図である。
1……原子炉状態量入力装置、2……プロセス
計算機、3……出力変動幅決定装置、4……リミ
ツタ、5……出力自動変更装置、6……原子炉。
The figure is a block diagram of an embodiment of the reactor power adjustment device of the present invention. DESCRIPTION OF SYMBOLS 1...Reactor state quantity input device, 2...Process computer, 3...Output fluctuation range determination device, 4...Limiter, 5...Output automatic change device, 6...Reactor.
Claims (1)
容範囲を計算する出力変動幅決定装置と、要求さ
れる出力変動の値が前記許容範囲内にあるか否か
を判断し、許容範囲内にある場合には、前記要求
される出力変動の値を、そのまま出力変動値とし
て出力し、許容範囲外となる場合には、許容範囲
の限界値を出力変動値として出力するリミツタ
と、前記出力変動値を入力し、この出力変動値に
基づいて、原子炉の出力変動を行なう出力変更装
置とを備えたことを特徴とする原子炉出力調整装
置。1. A power fluctuation range determination device that calculates the permissible range of power fluctuation that can maintain the integrity of the core state, and a device that determines whether the required power fluctuation value is within the permissible range, and determines whether the required power fluctuation value is within the permissible range. In some cases, a limiter outputs the requested output fluctuation value as it is as an output fluctuation value, and if it is outside the tolerance range, outputs a limit value of the tolerance range as the output fluctuation value; 1. A nuclear reactor output adjustment device comprising: an output changing device for inputting a value and changing the output of the reactor based on the output fluctuation value.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56011969A JPS57125895A (en) | 1981-01-29 | 1981-01-29 | Nuclear reactor power conditioning device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56011969A JPS57125895A (en) | 1981-01-29 | 1981-01-29 | Nuclear reactor power conditioning device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57125895A JPS57125895A (en) | 1982-08-05 |
| JPH0245160B2 true JPH0245160B2 (en) | 1990-10-08 |
Family
ID=11792438
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56011969A Granted JPS57125895A (en) | 1981-01-29 | 1981-01-29 | Nuclear reactor power conditioning device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57125895A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| NO335839B1 (en) | 2012-12-10 | 2015-03-02 | Jakob Hatteland Logistics As | Robot for transporting storage containers |
| NO337544B1 (en) | 2014-06-19 | 2016-05-02 | Jakob Hatteland Logistics As | Remote controlled vehicle assembly to pick up storage containers from a storage system |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5520404A (en) * | 1978-07-31 | 1980-02-13 | Nippon Atomic Ind Group Co | Load following automatic device of nuclear power plant |
-
1981
- 1981-01-29 JP JP56011969A patent/JPS57125895A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57125895A (en) | 1982-08-05 |
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