JPH03105286A - Operating method of reactor - Google Patents

Operating method of reactor

Info

Publication number
JPH03105286A
JPH03105286A JP1242115A JP24211589A JPH03105286A JP H03105286 A JPH03105286 A JP H03105286A JP 1242115 A JP1242115 A JP 1242115A JP 24211589 A JP24211589 A JP 24211589A JP H03105286 A JPH03105286 A JP H03105286A
Authority
JP
Japan
Prior art keywords
density
steam
coolant
reactor
decreases
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
Application number
JP1242115A
Other languages
Japanese (ja)
Inventor
Hiroki Sano
広樹 佐野
Koji Fujimura
幸治 藤村
Taisuke Bessho
別所 泰典
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP1242115A priority Critical patent/JPH03105286A/en
Publication of JPH03105286A publication Critical patent/JPH03105286A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To enable execution of stable starting by operating a reactor in the range of density wherein reactivity decreases or the range of density wherein it does not change. CONSTITUTION:A control rod 4 is in an inserted state at the time of starting, and it is pulled out with a flow rate of steam increased by a steam generating system 5. In a stage when the flow rate of steam reaches a rated value, a steam blower 2 and a recirculation pump 3 are started, the system 5 is cut off by steam selector valves 6a and 6b and the density of a coolant is increased by adjusting the flow proportioning of the steam and water. Since the reactivity increases and an output rises at this time, criticality is maintained with the control inserted. At the same time with this switching, a turbine 8 is rotated by a steam generator 7, while the steam is sent to a primary condenser 9, and the water is supplied by the recirculation pump 3. The density of the coolant is made to approach the density in a steady operation from a lower level, and the steady operation can be reached from safe starting.

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は原子炉、特に、冷却材単位体積に含まれる蒸気
の体積割合(ボイド率と称する)の増加に伴い、反応度
が増加する(ボイド係数(炉心からの中性子の漏れを含
む)が正と称する)特性範囲をもつ原子炉の運転方法に
係り,特に、原子炉出力を上昇,低下させるのに好適な
運転方法に関する。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to nuclear reactors, in particular nuclear reactors, in which the reactivity increases with an increase in the volume ratio of steam contained in a unit volume of coolant (referred to as void fraction). The present invention relates to a method of operating a nuclear reactor having a characteristic range in which the void coefficient (including leakage of neutrons from the reactor core) is referred to as positive, and particularly relates to an operating method suitable for increasing or decreasing reactor power.

〔従来の技術〕[Conventional technology]

従来の原子炉,例えば、沸騰水型原子炉(IlltlR
と称する)では,「原子炉講座』火力発電協会編(昭和
54年)第101頁に述べられているように、何らかの
原因で原子炉出力が上昇した場合、蒸気泡が増加するこ
とにより反応度が下がり、これにより出力増加がおさえ
られる自己安定性を持つている。
Conventional nuclear reactors, such as boiling water reactors (IlltlR
As stated in "Nuclear Reactor Course" edited by Thermal Power Generation Association (1978), p. 101, when the reactor output increases for some reason, the reactivity increases due to the increase in steam bubbles. It has self-stability, which suppresses the increase in output.

原子炉出力の増減は、この効果を利用し、原子炉再循環
流量及び給水流量の増減により行うことができる。すな
わち、再循環流量を増加させることにより、炉内のボイ
ド発生点を上方に移動し,炉心内のボイド体積が減少す
ることにより、反応度が増加する。これによって出力が
上昇すると蒸気量が増加,すなわち、ボイドが増加し、
反応度は抑えられる。
Utilizing this effect, the reactor output can be increased or decreased by increasing or decreasing the reactor recirculation flow rate and the feed water flow rate. That is, by increasing the recirculation flow rate, the point of void generation in the reactor is moved upward, and the void volume in the reactor core is reduced, thereby increasing the reactivity. As a result, as the output increases, the amount of steam increases, that is, the voids increase,
Reactivity can be suppressed.

このような特性は、原子炉の起動,停止時にも表れてお
り、流量にかかわらず、ボイドの体積増加により、冷却
材密度が小さくなると反応度が下がる(ボイド係数が負
)。
This characteristic also appears during the startup and shutdown of a nuclear reactor; regardless of the flow rate, the reactivity decreases (the void coefficient becomes negative) as the coolant density decreases due to an increase in void volume.

一方、軽水炉の高度化に伴い、一層のウラン利用率向上
を図るため、蒸気と水を冷却材として水素対重金属原子
数比を小さくすることにより、取り出される核分裂性物
質の投入した核分裂物質に対する比(転換比)を高めた
炉心概念(SWPR,Steam−Water Pow
ar Reactor)が1988年日ソセミナーで発
表されている。
On the other hand, as light water reactors become more sophisticated, in order to further improve the utilization rate of uranium, steam and water are used as coolants to reduce the hydrogen to heavy metal atomic ratio. (SWPR, Steam-Water Pow)
ar Reactor) was announced at the 1988 Japan-Soviet Seminar.

SWPRにおいては,冷却材密度を下げると反応度が上
がる(ボイド係数が正の)冷却材密度範囲がある点で、
従来の沸騰水型原子炉の特性と異なっている。この様子
を第2図を用いて説明する。
In SWPR, there is a range of coolant densities in which the reactivity increases when the coolant density is lowered (the void coefficient is positive).
The characteristics are different from those of conventional boiling water reactors. This situation will be explained using FIG. 2.

第2図は、SWPRの冷却材密度と反応度との関係を示
す.この図から分かるように、冷却材密度140kg/
m’付近を境とし、これより冷却材密度の低い範囲,す
なわち、高ボイド率の範囲では、冷却材密度が減少する
(ボイドが増加する)と反応度が低下する(ボイド係数
が負)。また、冷却材密度より高い密度範囲、すなわち
、低ボイド率の範囲では、冷却材密度が低下する(ボイ
ドが増加する)と反応度が増加する(ボイド係数が正)
Figure 2 shows the relationship between coolant density and reactivity for SWPR. As you can see from this figure, the coolant density is 140kg/
In a range where the coolant density is lower than m', that is, a high void ratio range, as the coolant density decreases (voids increase), the reactivity decreases (the void coefficient becomes negative). Also, in the density range higher than the coolant density, that is, in the range of low void fraction, as the coolant density decreases (voids increase), the reactivity increases (void coefficient is positive).
.

SWPRは、定常運転状態をこのボイド係数O付近(冷
却材密度140kg/rn’)に設定することにより、
ボイドが増減すると常に反応度が下がる固有の安全性を
持たせている特徴がる。
By setting the steady operating state to around this void coefficient O (coolant density 140 kg/rn'), SWPR
It has the inherent safety feature that the reactivity always decreases as the void increases or decreases.

しかし、このような炉心では、起動停止方法が未だ確立
していない. 〔発明が解決しようとする課題〕 上記SWPRのように、定常運転状態が,冷却材密度に
対する反応度変化が、ほとんどない密度範囲か、または
、冷却材密度の低減に伴い、反応度が低下する範囲(ボ
イド係数がOまたは負の範囲)にあり、起動時の冷却材
密度が,従来のBWRと同様に定常運転状態より高い範
囲にあるとすると、起動から定常運転に至るまで、ボイ
ド係数が正の範囲で運転することになり、起動時の運転
条件は従来のBWRに比べて厳しくなる。すなわち、出
力は冷却材密度を監視しながら制御棒を用いて準静的に
上昇させねばならず、定常運転まで非常に時間がかかる
However, a method for starting and stopping such a core has not yet been established. [Problem to be solved by the invention] As in the above SWPR, the steady operating state is a density range in which there is almost no change in reactivity with respect to coolant density, or the reactivity decreases as the coolant density decreases. range (with a void coefficient of O or a negative range), and if the coolant density at startup is higher than the steady-state operating state, similar to a conventional BWR, then from startup to steady-state operation, the void coefficient is The BWR will operate in the positive range, and the operating conditions at startup will be stricter than in conventional BWRs. That is, the output must be increased quasi-statically using control rods while monitoring the coolant density, and it takes a very long time to achieve steady operation.

本発明の目的は.SWPRのような特性をもった原子炉
の安全、かつ、迅速な起動装置を提偶することにある。
The purpose of this invention is. The object of the present invention is to provide a safe and quick start-up device for a nuclear reactor with characteristics similar to SWPR.

〔課題を解決するための手段〕[Means to solve the problem]

上記目的を達成するため↓こ,本発明は起動時の冷却材
密度状態を定常運転状態と同じ冷却材密度状態、すなわ
ち、冷却材密度が変化しても反応度が変化しない範囲、
もしくは、冷却材密度が減少すると反応度が減少する範
囲としたものである。
In order to achieve the above object, the present invention sets the coolant density state at startup to the same coolant density state as the steady operating state, that is, within the range where the reactivity does not change even if the coolant density changes.
Alternatively, the range is such that the reactivity decreases as the coolant density decreases.

また,起動時に減速材密度を達成するため、他システム
から熱,または、蒸気を供給するものである。
It also supplies heat or steam from other systems to achieve moderator density during startup.

また、起動に伴う反応度変化を制御するため、制御棒を
挿入しながら定常運転状態にする。
In addition, in order to control changes in reactivity due to startup, a control rod is inserted while maintaining steady operation.

さらに,原子炉停止時は、迅速に停止するため制御棒を
全挿入したのち、冷却材の密度が減少すると反応度が増
加する範囲で運転する。
Furthermore, when shutting down the reactor, in order to shut down the reactor quickly, the control rods are fully inserted and then the reactor is operated in a range where the reactivity increases as the density of the coolant decreases.

〔作用〕[Effect]

すなわち,起動時に、冷却材密度がボイド係数0,また
は、負の範囲にあれば、定常運転時にもボイド係数はO
または負の範囲にあるため、起動から定常運転時まで,
常に、ボイド係数0,または,負の範囲で運転すること
になり、現行BWRと同様に安全な運転となる。また、
このため起動から定常運転に至る時間は短くできる。
In other words, if the coolant density is in the void coefficient 0 or in the negative range at startup, the void coefficient is O even during steady operation.
or in the negative range, from startup to steady operation.
The vehicle always operates with a void coefficient of 0 or in a negative range, resulting in safe operation similar to the current BWR. Also,
Therefore, the time from startup to steady operation can be shortened.

この冷却材密度を、原子炉出力の出ない起動時から実現
するためには,他の熱、または、蒸気発生システムによ
り蒸気、または、蒸気と水の二相流を送り込めばよい。
In order to achieve this coolant density even during startup, when the reactor is not producing power, steam or a two-phase flow of steam and water can be delivered using other heat or steam generation systems.

さらに、停止時には、通常起動時と逆の手順で運転する
が、ボイド係数正の範囲を用いることにより、すばやく
停止できる。すなわち,まず、制御棒を全挿入して反応
度を下げると出力が低下し、冷却材の密度が増加する。
Furthermore, when stopping, the operation is performed in the reverse order of normal starting, but by using the positive void coefficient range, it is possible to stop quickly. That is, first, when the control rods are fully inserted to lower the reactivity, the output decreases and the density of the coolant increases.

これにより,さらに反応度が下がるため迅速に停止する
ことができる。
This further reduces the degree of reactivity, so it can be stopped quickly.

〔実施例〕〔Example〕

以下、本発明の一実施例を第l図により説明する。 An embodiment of the present invention will be described below with reference to FIG.

第1図は本発明の原子炉運転方法をSWPRに適用する
場合に好適なシステム構成を示す。SリPRは炉心1,
蒸気ブロア2,@環ポンプ3、制御棒4等により構威さ
れている。また、炉心特性として冷却材密度による反応
度の変化を見ると,第2図に示すように、冷却材密度が
増加すると反応度が増加するボイド係数が正の範囲と、
冷却材密度が増加すると反応度が減少するボイド係数が
負の範囲の両方を取り得る。また,定常運転時には、ボ
イド係数がほぼOとなる約1 4 0kg/rn’ (
1 6M P a )の冷却材密度となっている。
FIG. 1 shows a system configuration suitable for applying the nuclear reactor operating method of the present invention to SWPR. S-PR is core 1,
It is composed of a steam blower 2, a ring pump 3, a control rod 4, etc. Also, when we look at the change in reactivity due to coolant density as a core characteristic, as shown in Figure 2, the void coefficient, where the reactivity increases as the coolant density increases, is in the positive range.
As the coolant density increases, the reactivity decreases and the void coefficient can take on both negative ranges. Also, during steady operation, the void coefficient is approximately 0, about 140kg/rn' (
The coolant density is 16 MPa).

本実施例は、このボイド係数負の範囲で起動させるため
に、他の蒸気発生システム5を備えている。蒸気発生シ
ステム5は他のタイプの炉、または、化石燃料を使った
ボイラ等である。
This embodiment includes another steam generation system 5 in order to operate in this negative void coefficient range. The steam generation system 5 may be another type of furnace or a fossil fuel boiler.

起動時には、制御棒4は挿入された状態にあり、蒸気発
生システム5により、蒸気流量を増加しながら制御棒4
を引き抜いていく。蒸気流量が定格値となった段階で,
蒸気ブロア2,再循環ボンプ3を起動して、蒸気切換弁
6a,6bでシステム5をしゃ断し、蒸気と水の流量配
分を調整して冷却材密度を上げていく。このとき、反応
度が上がり,出力が上昇するので、制御棒を挿入しなが
ら臨界を保つ。また,この切り換えとともに、蒸気発生
器7でタービン8を回すとともに一次復水器9へ蒸気を
送り、循環ボンプ3で水を送る。
At startup, the control rod 4 is in the inserted state, and the steam generation system 5 causes the control rod 4 to increase while increasing the steam flow rate.
I'm going to pull it out. When the steam flow rate reaches the rated value,
The steam blower 2 and recirculation pump 3 are started, the system 5 is shut off by the steam switching valves 6a and 6b, and the flow distribution of steam and water is adjusted to increase the coolant density. At this time, the reactivity increases and the output increases, so criticality is maintained while inserting the control rod. At the same time, the steam generator 7 turns the turbine 8 and sends steam to the primary condenser 9, and the circulation pump 3 sends water.

このとき、第2図では冷却材密度の低い方から定常運転
時の密度に近づけることになる。すなわち,本実施例で
は冷却材密度の減少に伴い反応度が減少する範囲(冷却
材密度の増加に伴い反応度が増加する範囲)で起動から
定常運転に至ることができる。この範囲では負のボイド
係数をもっているため、安全に起動し、定常運転に至る
ことができる。
At this time, in FIG. 2, the lower coolant density approaches the density during steady operation. That is, in this embodiment, it is possible to reach steady operation from startup within the range where the reactivity decreases as the coolant density decreases (the range where the reactivity increases as the coolant density increases). Since it has a negative void coefficient in this range, it can be started safely and steady operation can be achieved.

次に、本発明の第二の原子炉起動に関する実施例を第1
図を用いて示す。第一の実施例では他の蒸気発生システ
ム5により完全な蒸気(ボイド率100%)を起動時に
送り込んでいたが、冷却材密度がボイド係数負の範囲に
あれば最初から水と混合させておくことも可能である。
Next, a first embodiment of the second nuclear reactor startup of the present invention will be described.
Illustrated using diagrams. In the first embodiment, complete steam (void ratio 100%) was sent by another steam generation system 5 at startup, but if the coolant density is in the negative void coefficient range, it is mixed with water from the beginning. It is also possible.

すなわち、本実施例では起動時にシステム5を動かすと
ともに、循環ポンプ3を作動する。この時、注入ざれる
混合流では、蒸気の水に対する混合割合が,定常運転時
のそれより大きくなるように循環ポンプ流量を調整する
。これにより、冷却材密度は定常運転時より小さくでき
、安全な起動が可能になる。
That is, in this embodiment, at the time of startup, the system 5 is operated and the circulation pump 3 is operated. At this time, in the injected mixed flow, the circulation pump flow rate is adjusted so that the mixing ratio of steam to water is greater than that during steady operation. This allows the coolant density to be lower than during steady operation, allowing safe startup.

本実施例の起動から定常運転に至る手順は第1の実施例
と同じく、まず、蒸気の水に対する割合が定常運転時よ
り大きな冷却材密度範囲で制御棒を引き抜かれた状態と
する。次に,水の蒸気に対する割合を増加させていきな
がら、臨界を保つため制御棒を挿入していく。本方法で
は最初から水を混合させておくため、起動から定常運転
に至る時間をさらに短くできる効果がある。
The procedure from startup to steady operation in this embodiment is the same as in the first embodiment; first, the control rod is pulled out in a coolant density range in which the ratio of steam to water is greater than that during steady operation. Next, control rods are inserted to maintain criticality while increasing the ratio of water to steam. Since this method mixes water from the beginning, it has the effect of further shortening the time from startup to steady operation.

なお、減速材密度が定常運転時のそれに近ければ反応度
はほとんど変化せず、ボイド係数がほぼOとなっている
が、このような場合でも出力係数は負であり安全である
Note that if the moderator density is close to that during steady operation, the reactivity hardly changes and the void coefficient is approximately O, but even in such a case, the output coefficient is negative and safe.

次に、本発明の第一の原子炉停止に関する運転方法の実
施例を第1図を用いて説明する。
Next, an embodiment of the first operating method regarding nuclear reactor shutdown of the present invention will be described using FIG. 1.

ボイド係数負の通常の原子炉では、停止は起動と逆手順
で行われるが、本炉のように、ボイド係数が正負両方を
取り得る炉心では,さらに迅速に停止させるためボイド
係数が正の範囲(冷却材密度が減少すると反応度が増加
する範囲)で停止できる。
In a normal nuclear reactor with a negative void coefficient, shutdown is performed in the reverse order of startup, but in a core like this reactor where the void coefficient can be both positive and negative, the void coefficient is within a positive range in order to shut down even more quickly. It can be stopped in the range where the reactivity increases as the coolant density decreases.

すなわち、まず、制御棒4を挿入して、反応度を下げて
未臨界とし,その後,流量配分を調整して蒸気ブロア2
からの給供を少なくしていく。これにより冷却材密度が
増加するため反応度が,さらに、下がり,原子炉を迅速
に停止することができる。
That is, first, the control rod 4 is inserted to lower the reactivity to make it subcritical, and then the flow rate distribution is adjusted and the steam blower 2
We will reduce the supply from This increases the coolant density, further lowering the reactivity and allowing the reactor to be shut down quickly.

なお,迅速ではないが、原子炉停止は通常のように起動
と逆手順で行うこともできる。
Although it is not quick, reactor shutdown can also be performed in the reverse order of startup as usual.

なお、本発明は特にSWPRについての適用例を示した
が、同様の特性を持つすべての炉心について適用可能で
ある。
Although the present invention has been specifically applied to SWPR, it is applicable to all cores having similar characteristics.

〔発明の効果〕〔Effect of the invention〕

本発明によれば,未だ確立されていない、ボイド係数が
正の冷却材密度範囲のある炉心について、迅速、かつ、
安全に起動・停止することができる。
According to the present invention, for a core with a coolant density range with a positive void coefficient that has not yet been established, it is possible to quickly and
It can be started and stopped safely.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本発明の一実施例の系統図,第2図は,SWP
Rの冷却材密度に対する反応度の変化を表す図である。 1・・・炉心、2・・・蒸気ブロア、3・・・再循環ポ
ンプ、4・・・制御棒、5・・・蒸気発生システム、6
a,6b・・・蒸気切換弁、7・・・蒸気発生器、8・
・・タービン,第 1 図 第2図 冷Ep材酵贋r(り/π3冫
Figure 1 is a system diagram of an embodiment of the present invention, Figure 2 is a system diagram of an embodiment of the present invention.
FIG. 3 is a diagram showing a change in reactivity of R with respect to coolant density. DESCRIPTION OF SYMBOLS 1... Reactor core, 2... Steam blower, 3... Recirculation pump, 4... Control rod, 5... Steam generation system, 6
a, 6b...Steam switching valve, 7...Steam generator, 8.
...Turbine, Fig. 1 Fig. 2 Cold Ep material fermentation r(ri/π3冫

Claims (1)

【特許請求の範囲】 1、炉心を流れる冷却材密度の減少に伴い、反応度が増
加する密度範囲と、減少する密度範囲もしくは変化しな
い密度範囲とがあり、出力がほぼ一定の目標出力となる
定常運転時には、前記冷却材密度の減少により、反応度
が減少する密度範囲、もしくは、変化しない密度範囲に
ある特徴を持つ原子炉において、 制御棒と冷却材流量の制御により、目標出力まで出力を
増加させる起動時にも、前記炉心を流れる前記冷却材密
度の減少に伴い、前記反応度が減少する密度範囲、もし
くは、変化しない密度範囲において運転することを特徴
とする原子炉の運転方法。 2、請求項1において、前記原子炉の出力を低下させ、
前記原子炉を停止する際に、前記冷却材密度が減少する
に伴い、反応度が増加する密度範囲で運転することを特
徴とする原子炉の運転方法。 3、蒸気−水の混合流を冷却材として用いる、原子炉に
おいて、前記原子炉の起動時には、蒸気の水に対する割
合が、定常運転時のそれ以上とすることを特徴とする原
子炉運転方法。 4、請求項3において、起動時には制御棒を定常運転時
に比べて引き抜いた状態とし、目標出力となるまで、蒸
気に対する水の割合を増加させながら、制御棒を挿入す
ることを特徴とする原子炉の運転方法。 5、請求項2において、定常運転時から停止に至る手順
として、制御棒を未臨界となるまで挿入したのち、流量
を減少することを特徴とする原子炉運転方法。 6、請求項1に記載の原子炉の起動時に、他のシステム
から熱、または、蒸気を供給することにより、冷却材密
度が減少すると反応度が減少する密度範囲に設定するこ
とを特徴とする原子炉の運転方法。 7、請求項1において、停止時の冷却材の密度範囲は起
動時のそれと同じとし、停止手順は、第1項請求範囲記
載の起動時の運転方法と逆手順であることを特徴とする
原子炉の運転方法。
[Claims] 1. As the density of the coolant flowing through the reactor core decreases, there is a density range in which the reactivity increases, and a density range in which it decreases or does not change, and the output becomes a nearly constant target output. During steady operation, in a nuclear reactor characterized by a density range in which the reactivity decreases due to the decrease in coolant density, or in a density range where it does not change, the output is increased to the target output by controlling the control rods and the coolant flow rate. A method for operating a nuclear reactor, comprising operating in a density range in which the reactivity decreases or does not change as the density of the coolant flowing through the reactor core decreases even during startup. 2. In claim 1, reducing the output of the nuclear reactor,
A method for operating a nuclear reactor, characterized in that when the reactor is shut down, the reactor is operated in a density range in which reactivity increases as the coolant density decreases. 3. A nuclear reactor operating method in which a mixed flow of steam and water is used as a coolant, characterized in that when the reactor is started up, the ratio of steam to water is higher than that during steady operation. 4. The nuclear reactor according to claim 3, wherein the control rods are pulled out at startup compared to during steady operation, and the control rods are inserted while increasing the ratio of water to steam until the target output is reached. How to drive. 5. A nuclear reactor operating method according to claim 2, characterized in that the flow rate is reduced after the control rods are inserted until the reactor becomes subcritical as a procedure from steady operation to shutdown. 6. At the time of startup of the nuclear reactor according to claim 1, heat or steam is supplied from another system to set a density range in which the reactivity decreases as the coolant density decreases. How to operate a nuclear reactor. 7. In claim 1, the density range of the coolant at the time of shutdown is the same as that at startup, and the shutdown procedure is a reverse procedure to the operating method at startup described in claim 1. How to operate a furnace.
JP1242115A 1989-09-20 1989-09-20 Operating method of reactor Pending JPH03105286A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1242115A JPH03105286A (en) 1989-09-20 1989-09-20 Operating method of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1242115A JPH03105286A (en) 1989-09-20 1989-09-20 Operating method of reactor

Publications (1)

Publication Number Publication Date
JPH03105286A true JPH03105286A (en) 1991-05-02

Family

ID=17084523

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1242115A Pending JPH03105286A (en) 1989-09-20 1989-09-20 Operating method of reactor

Country Status (1)

Country Link
JP (1) JPH03105286A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8807438B2 (en) 2006-02-22 2014-08-19 Toyo Seikan Kaisha, Ltd. RFID tag substrate for metal component

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8807438B2 (en) 2006-02-22 2014-08-19 Toyo Seikan Kaisha, Ltd. RFID tag substrate for metal component

Similar Documents

Publication Publication Date Title
US6343106B1 (en) Boiling water reactor and operation thereof
Hu et al. Commissioning and operation experience and safety experiments on HTR-10
JPH03105286A (en) Operating method of reactor
US20090141847A1 (en) Method for operating nuclear power generation plant and nuclear power generation plant
JP5352375B2 (en) Reactor power controller
JP3133812B2 (en) Boiling water reactor and start-up method thereof
JPH0361159B2 (en)
JP4556883B2 (en) Reactor power controller
JP4521367B2 (en) Reactor power control method and reactor plant
JPH0529278B2 (en)
JP3362603B2 (en) Reactor power control device
JPS5828689A (en) Method and device for controlling reactor power at load loss
JP3085715B2 (en) Reactor operation method
SHIMIZU et al. Power Maneuvering Method to Enhance Compatibility with Renewables and Core Design to Improve Pu Utilization for Advanced Light Water Reactor SRZ®-1200
JP2024063575A (en) How to control the reactor core
Zhang et al. Optimization Research on Reactor Control System Under Mode-C Operation Control Mode
CN116260195A (en) A method for nuclear power plants to prevent reactor overpower caused by primary frequency modulation
JPS5928696A (en) Reactor control device
Hui et al. Robust burn control of fusion reactors with modulation of refueling rate
Gul et al. Technical support to an operating PWR vis-à-vis safety analysis
JPS5818200A (en) Passive type emergency shutdown device for pwr type reactor
KR810001338B1 (en) Reactor operation to control low follow
JP2020187061A (en) Control apparatus of nuclear power plant, nuclear power plant, and control method for nuclear power plant
JPS61193098A (en) Nuclear power plant and operation method thereof
JPS6262310B2 (en)