JPH053556B2 - - Google Patents
Info
- Publication number
- JPH053556B2 JPH053556B2 JP59079651A JP7965184A JPH053556B2 JP H053556 B2 JPH053556 B2 JP H053556B2 JP 59079651 A JP59079651 A JP 59079651A JP 7965184 A JP7965184 A JP 7965184A JP H053556 B2 JPH053556 B2 JP H053556B2
- Authority
- JP
- Japan
- Prior art keywords
- output
- core
- control rod
- point
- outermost
- 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
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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)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
Description
【発明の詳細な説明】
[発明の技術分野]
本発明は沸騰水型原子炉(以下BWRと称す)
の運転方法に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a boiling water reactor (hereinafter referred to as BWR).
Regarding how to drive.
[発明の技術的背景]
第1図乃至第5図を参照して従来例を説明す
る。第1図はBWRの概略構成を示す縦断面図で
ある。図中符号1は原子炉圧力容器を示し、この
原子炉圧力容器1内には炉心2および冷却材3が
収容されている。上記炉心2は複数の燃料集合体
4および第2図に示す制御棒5等から構成されて
いる。上記冷却材3は上記炉心2を下方から上方
に向つて流通しその際炉心2の核反応熱により昇
温して水と蒸気の二層流状態となる。二層流状態
となつた冷却材3は炉心2の上方に設置された気
水分離器6内に流入して水と蒸気に分離される。
分力容器1と同心上に設置されたシユラウド9内
に収容されており、また上記シユラウド9と原子
炉圧力容器1との間のダウンカマ部10にはジエ
ツトポンプ11が等間隔に複数台設置されてい
る。このジエツトポンプ11は再循環系入口ノズ
ル12および再循環系出口ノズル13を介して配
設される図示しない再循環配管およびこの再循環
配管に介挿される図示しない再循環ポンプとで再
循環系を構成しており、冷却材3を炉心2に強制
循環させている。なお図中符号14は給水ノズル
を示し、符号15は炉心スプレイスパージヤを示
しまた符号16は前記制御棒5を炉心2内に挿
入、引抜する制御棒駆動機構を示す。[Technical Background of the Invention] A conventional example will be described with reference to FIGS. 1 to 5. FIG. 1 is a longitudinal sectional view showing the schematic configuration of the BWR. In the figure, reference numeral 1 denotes a reactor pressure vessel, in which a reactor core 2 and a coolant 3 are housed. The reactor core 2 is composed of a plurality of fuel assemblies 4, control rods 5 shown in FIG. 2, and the like. The coolant 3 flows through the reactor core 2 from below to above, and as it does so, its temperature increases due to the heat of nuclear reaction in the reactor core 2, resulting in a two-layer flow state of water and steam. The coolant 3 in a two-layer flow state flows into a steam-water separator 6 installed above the core 2 and is separated into water and steam.
It is housed in a shroud 9 installed concentrically with the force component vessel 1, and a plurality of jet pumps 11 are installed at equal intervals in the downcomer section 10 between the shroud 9 and the reactor pressure vessel 1. There is. This jet pump 11 constitutes a recirculation system with a recirculation pipe (not shown) disposed through a recirculation system inlet nozzle 12 and a recirculation system outlet nozzle 13, and a recirculation pump (not shown) inserted into this recirculation pipe. The coolant 3 is forced to circulate through the core 2. In the figure, reference numeral 14 indicates a water supply nozzle, reference numeral 15 indicates a core spray spargeer, and reference numeral 16 indicates a control rod drive mechanism for inserting and withdrawing the control rod 5 into the reactor core 2.
上記炉心2は第2図に示すように構成されてい
る。第2図は炉心2の一部平面図である。すなわ
ち4体の燃料集合体4を断面が十字型の制御棒5
の周囲に配置して単位格子21を構成し、この単
位格子21をさらに格子状に配列した構成であ
る。 The reactor core 2 is constructed as shown in FIG. FIG. 2 is a partial plan view of the reactor core 2. FIG. In other words, four fuel assemblies 4 are connected to control rods 5 having a cross-shaped cross section.
The structure is such that a unit cell 21 is arranged around the periphery of the unit cell 21, and this unit cell 21 is further arranged in a lattice shape.
このようなBWRにおいては、核分裂性物質、
あるいはその娘核として生成されたゼノンの中性
子吸収能力が大きい為にゼノンが全く存在しない
起動開始時と、ゼノンが飽和に達した定格運転時
とではゼノンが寄与する反応度効果が2.5%ΔK/
K程度異なり、その為原子炉の機動あるいは再起
動を考える上で上記ゼノン濃度が重要な意味を有
する。 In such a BWR, fissile material,
Alternatively, since the neutron absorption capacity of Zenon produced as a daughter nucleus is large, the reactivity effect contributed by Zenon is 2.5% ΔK/
Therefore, the above-mentioned xenone concentration has an important meaning when considering the operation or restart of a nuclear reactor.
すなわち原子炉の起動開始時において、ゼノン
が殆無い状態で前記制御棒5を引抜いた場合に
は、制御棒5を炉心定格出力レベルを実現するの
に必要とされる制御棒パターンまで引抜く以前に
出力が大幅に上昇してしまう。このように制御棒
5の引抜量が少ない状態で炉心出力を上昇させる
と、引抜かれた制御棒5の割合が少ない為発熱が
上記引抜かれた制御棒5に対応した燃料集合体4
に集中してこの部分に局所的過出力部分が発生す
る。 In other words, if the control rods 5 are pulled out with almost no Zenon at the start of reactor startup, before the control rods 5 are pulled out to the control rod pattern required to achieve the core rated output level. The output will increase significantly. When the core power is increased in a state where the amount of control rods 5 that have been pulled out is small in this way, the proportion of control rods 5 that have been pulled out is small, so that heat generation is caused by the fuel assemblies 4 corresponding to the control rods 5 that have been pulled out.
A local over-output portion occurs in this area.
また一般に燃料の設計にあたつては定格時の飽
和ゼノンの状態で適切な出力分布となるように行
なわれており、ゼノンが無い状態ではボイドの発
生がない炉心下部の出力が大幅に大きくなるとい
う問題がある。そして原子炉の運転にあたつては
一般に燃料の健全性を確保する為に、炉心慣し運
転の為の法案(以後PCIOMR基準と称す)が設
定されており、燃料の出力に制限値(以後PCエ
ンベロープと称す)を設けている。よつてゼノン
が無い状態で急激に出力を上昇させると、前述し
たように局所的な出力上昇が発生し、上記PCエ
ンベロープを越えてしまうことがある。したがつ
て炉心出力上昇時にはゼノンの蓄積をまつて順次
出力を増加させることが必要である。 In addition, fuel is generally designed to provide an appropriate power distribution in the saturated Zenon state at the rated time, and in the absence of Zenon, the power output in the lower part of the core where voids do not occur will be significantly greater. There is a problem. In order to generally ensure the integrity of the fuel when operating a nuclear reactor, a law for core break-in (hereinafter referred to as PCIOMR standards) has been established, and a limit value (hereinafter referred to as PCIOMR standard) has been established for the fuel output. (referred to as the PC envelope). Therefore, if the output is suddenly increased without Zenon, a local increase in output will occur as described above, and the PC envelope may be exceeded. Therefore, when the core power increases, it is necessary to wait for the accumulation of Zenon and gradually increase the power.
ところで前述したような構成のBWRにおいて
炉心出力の制御は再循環系による再循環流量の調
整により行なう方法と、制御棒駆動機構15によ
り制御棒5を操作して行なう方法の二通りの方法
により行なわれている。そして起動時には制御棒
5を全挿入の状態から順次引抜いて定格運転用制
御棒パターンとする。しかしこの間に実施される
制御棒パターンによつては局所出力分布が大きく
ひずみ、前記PCエンベロープを越える場合があ
り得るので、かかる場合にはゼノン濃度の増加を
利用して出力を低下させる必要がある。一方前記
再循環系によつて再循環流量を制御することによ
り炉心出力を制御する場合には、前記PCIOMR
基準がある規定値以下の出力上昇率であれば上記
PCエンベロープを越えた出力上昇を許容してい
る為、出力を徐々に増加させることが可能であ
り、PCIOMR基準で決められた設定値以上に出
力を上昇させることが可能である。 By the way, in the BWR configured as described above, the core power is controlled in two ways: by adjusting the recirculation flow rate using the recirculation system, and by operating the control rods 5 using the control rod drive mechanism 15. It is. At startup, the control rods 5 are sequentially pulled out from the fully inserted state to obtain a control rod pattern for rated operation. However, depending on the control rod pattern implemented during this time, the local power distribution may be greatly distorted and exceed the PC envelope, so in such cases it is necessary to reduce the power by utilizing the increase in Zenone concentration. . On the other hand, when controlling the core power by controlling the recirculation flow rate using the recirculation system, the PCIOMR
If the output increase rate is below a specified value, the above applies.
Since it allows the output to rise beyond the PC envelope, it is possible to gradually increase the output, and it is possible to increase the output beyond the set value determined by the PCIOMR standard.
かかる状況の基に従来、原子炉起動時の運転で
は運転の簡便さを優先させ制御棒5を十分低い出
力レベルで引抜くことができるように低出力運転
を長時間継続させている。そのため原子炉の起動
に長時間を要するという問題があつた。そこで起
動に要する時間を短縮させることを目的として、
第3図に示すような運転方法が考えられている。
第3図は横軸に時間(日)をとり、縦軸に炉心出
力をとり炉心出力の時間変化を示した図である。
なお図中実線太線は制御棒5の引抜により炉心出
力を上昇させた場合を示し、また破線は炉心流量
の調整によつて炉心出力を制御した場合を示す。
図中O1点で発電機を併入し、制御棒5を引抜い
て図中A1点まで出力を浄昇させる。その状態で
図中B1点まで出力を保持する。このような一定
時間の出力保持は定期検査後の初起動では必要と
されており、この間に例えば交換された機器の機
能の健全性等を検査する。そして所定時間出力を
保持した後制御棒5を引抜いて図中C1点まで出
力を急速上昇させる。その際C1点における制御
棒パターンの一実施例を第4図に示す。この第4
図は炉心2を模式的に示した平面図であり、1つ
の升目が前記単位格子21を示す。また各升目内
に記載された数字は制御棒5の挿入、引抜状態を
示す数字で全挿入の状態をOで示し、全引抜の状
態を48で示し、数が多い程制御棒5が多く引抜
かれていることを示している。なお第4図中数字
の記載のない位置の制御棒5は全て全引抜状態に
ある。このC1点での制御棒パターンは前記
PCIOMR基準を遵守することができること、お
よびゼノンの蓄積がない為に反応度補償機能を果
たすことが必要とされる。その為第4図にも示す
ように中央部に位置する制御棒5は浅く挿入され
ており、また最外周に位置している制御棒5は全
挿入されている。次に上記C1点からD1点を介
してE1点までは、炉心流量の調整(具体的には
炉心流量の増大)により出力を上昇させるととも
に、ゼノンの蓄積を行なう。その後炉心流量を低
下させることにより、図中F1点まで出力を低下
させる。ここに出力の低下を行なうのは次に制御
棒5を操作して出力を上昇させる場合、局所的に
出力が上昇して前記PCエンベロープを越えると
いつた事態を未然に防止する為である。出力を低
下させた後第5図に示す目標制御棒パターンを作
製するべく上記中央部の浅挿入制御棒5および最
外周制御棒5の引抜を行ない図中G1点まで出力
を上昇させる。以降炉心流量の調整により図中I
1点まで出力を上昇させて定格出力状態を得る。 Under such circumstances, conventionally, when starting up a nuclear reactor, priority has been given to ease of operation, and low power operation is continued for a long time so that the control rods 5 can be pulled out at a sufficiently low power level. As a result, there was a problem in that it took a long time to start up the reactor. Therefore, in order to shorten the time required for startup,
An operating method as shown in FIG. 3 has been considered.
FIG. 3 is a diagram showing time changes in core power, with time (days) plotted on the horizontal axis and core power plotted on the vertical axis.
Note that the solid thick line in the figure shows the case where the core power is increased by withdrawing the control rod 5, and the broken line shows the case where the core power is controlled by adjusting the core flow rate.
A generator is connected at point O1 in the figure, and the control rod 5 is pulled out to increase the output to point A1 in the figure. In this state, the output is maintained up to point B1 in the figure. Such output retention for a certain period of time is required at the first startup after a periodic inspection, and during this period, for example, the functional soundness of the replaced equipment is inspected. After maintaining the output for a predetermined time, the control rod 5 is pulled out and the output is rapidly increased to point C1 in the figure. An example of the control rod pattern at point C1 is shown in FIG. This fourth
The figure is a plan view schematically showing the reactor core 2, and one square represents the unit cell 21. In addition, the numbers written in each square indicate the insertion and withdrawal states of the control rods 5. The fully inserted state is indicated by O, and the fully withdrawn state is indicated by 48. The larger the number, the more the control rods 5 are pulled out. It shows that it has been removed. Note that the control rods 5 at positions without numbers in FIG. 4 are all in a fully withdrawn state. The control rod pattern at this C1 point is as described above.
It is required to be able to comply with the PCIOMR standard and to perform the reactivity compensation function due to the absence of xenone accumulation. Therefore, as shown in FIG. 4, the control rod 5 located at the center is inserted shallowly, and the control rod 5 located at the outermost periphery is fully inserted. Next, from the C1 point to the E1 point via the D1 point, the output is increased by adjusting the core flow rate (specifically, by increasing the core flow rate), and Zenon is accumulated. Thereafter, by lowering the core flow rate, the output is lowered to point F1 in the figure. The reason for reducing the output here is to prevent a situation in which the output increases locally and exceeds the PC envelope when the control rod 5 is operated to increase the output next time. After reducing the output, the shallowly inserted control rod 5 at the center and the outermost control rod 5 are pulled out to create the target control rod pattern shown in FIG. 5, and the output is increased to point G1 in the figure. After that, by adjusting the core flow rate, I
Increase the output to 1 point to obtain the rated output state.
[背景技術の問題点]
上記構成において目標の出力状態を得る前の操
作としてE1点からF1点までの出力降下および
その後の制御棒5の引抜操作が必要となり、その
為目標の出力状態を得るまでに長時間を必要とし
てしまい、また上記F1点からG1点まで出力を
上昇させる為に制御棒5を引抜く際前記
PCIOMR基準の基に十分な監視が必要となると
ともにゼノン濃度が複雑に変化しまた制御棒操作
に伴う局所出力分布の変化が大きい為操作に困難
を要してしまうという不具合があつた。[Problems with the background art] In the above configuration, it is necessary to lower the output from the E1 point to the F1 point and then pull out the control rod 5 as an operation before obtaining the target output state, so that the target output state is obtained. In addition, when pulling out the control rod 5 in order to increase the output from the F1 point to the G1 point, the above-mentioned
In addition to requiring sufficient monitoring based on the PCIOMR standards, there were also problems in that the xenone concentration changed in a complicated manner, and the local power distribution varied greatly with control rod operations, making operation difficult.
本発明は以上の点に基づいてなされたものでそ
の目的とするところは短時間で目標の炉心出力状
態を得ることを可能とする沸騰水型原子炉の運転
方法を提供することにある。
The present invention has been made based on the above points, and its purpose is to provide a method of operating a boiling water reactor that makes it possible to obtain a target core power state in a short period of time.
すなわち本発明による沸騰水型原子炉の運転方
法は、炉心から所定の制御棒を引抜いて原子炉の
起動運転を行う際に、前記炉心の最外周に位置す
る最外周制御棒の引抜き本数を相対ゼノン濃度に
応じて決定し、前記相対ゼノン濃度が低い時には
前記最外周制御棒の引抜き本数を少なくして起動
運転を行い、その後前記炉心に挿入されている最
外周制御棒を徐々に引抜き目標制御棒パターンと
することを特徴とする。
That is, in the boiling water reactor operating method according to the present invention, when predetermined control rods are pulled out from the reactor core and the reactor is started up, the number of the outermost control rods to be pulled out, which are located at the outermost periphery of the core, is relative to the number of control rods to be pulled out. It is determined according to the xenone concentration, and when the relative xenone concentration is low, the number of the outermost control rods to be pulled out is reduced to perform startup operation, and then the outermost control rods inserted in the reactor core are gradually pulled out to perform target control. It is characterized by a bar pattern.
第6図乃至第9図を参照して本発明の一実施例
を説明する。第6図は横軸に時間(日)をとり縦
軸に炉心出力をとり炉心出力の時間変化を示す線
図である。まず図中O2点で発電機を伴入し、制
御棒5を引抜いて図中A2点まで出力を上昇させ
る。この状態で出力を図中B2まで一定保持す
る。このように出力を一定時間保持するのは前述
した通りである。次にB2点から図中C2点まで
出力を上昇させる。その際上記C2点における制
御棒5の状態が第7図に示すようなパターンにな
るように制御棒5の引抜を行なう。すなわちB2
点からC2点に到る間はゼノンの蓄積が無く、そ
こで炉心2の最外周に位置する最外周制御棒5の
挿入本数をC2点において従来より多くなるよう
に制御棒5の引抜操作を行ない、これによつてゼ
ノン不足による反応度を補償しようとするもので
ある。またその時C2点での最外周制御棒5の挿
入本数は以下のようにして決定される。すなわち
第8図に示すように最外周に位置する最外周制御
棒5を夫々符号a,b,c,dで示す。ここにa
で示す最外周制御棒5は4本であり、bで示す最
外周制御棒5は8本、Cで示す最外周制御棒5は
8本、dで示す最外周制御棒5は4本である。そ
してこれらa,b,c,dで示された最外周制御
棒5を相対ゼノン濃度に対応させて適宜組合わせ
その本数を決定する。第9図は横軸にC2点で最
終的に挿入状態にある最外周制御棒5の本数をと
り縦軸に相対ゼノン濃度をとり、相対ゼノン濃度
とC2点で挿入状態にある最外周制御棒5の本数
との関係を示した図である。そして例えばC2点
でのゼノン濃度がeであると予想される場合に
は、C2点で最終的に第8図中aで示される最外
周制御棒5が挿入された状態になるように制御棒
5の引抜操作を行なう。またC2点でのゼノン濃
度がfであると予想される場合には第8図中bで
示す最外周制御棒5が最終的に挿入状態にあるよ
うに制御棒5の引抜操作を行なう。以下ゼノン濃
度がg,h,i,jの場合にも同様に最終的に挿
入状態にある最外周制御棒5の本数が決定され
る。本実施例の場合にはゼノン濃度がiの場合を
想定して示してある。よつて前記第7図において
a,b,cの位置に対応した最外周制御棒5が挿
入されている。なおこの時前記PCIOMR基準を
樛守できるような制御棒操作であることは勿論で
ある。次にC2点以降はゼノンが徐々に蓄積され
ていくため、PCIOMR基準上余裕が発生し、よ
つて挿入状態にある最外周制御棒5を徐々に引抜
いて前記第5図に示した目標制御棒パターンとし
出力の上昇を図る。その際の制御棒5の引抜量は
次のような量である。すなわち制御棒5を軸方向
に24分割し、その内の1分割に相当する軸方向
距離を最少制御棒駆動単位とすると、1時間に3
最少制御棒駆動単位ずつ引抜いていく。かかる操
作も上記PCIOMR基準を確実に遵守しながら出
力の上昇を図る為である。そしてこのような制御
棒操作により第6図中E2点まで出力を上昇させ
る。E2点以降は炉心流量の調整によりF2点を
介してG2点まで出力を上昇させ、定格出力状態
を得る。
An embodiment of the present invention will be described with reference to FIGS. 6 to 9. FIG. 6 is a diagram showing time changes in core power, with time (days) on the horizontal axis and core power on the vertical axis. First, a generator is brought in at point O2 in the figure, and the control rod 5 is pulled out to increase the output to point A2 in the figure. In this state, the output is held constant up to B2 in the figure. The reason why the output is held for a certain period of time in this way is as described above. Next, the output is increased from point B2 to point C2 in the figure. At this time, the control rod 5 is pulled out so that the state of the control rod 5 at the C2 point becomes a pattern as shown in FIG. That is, B2
There is no accumulation of Zenon from point C2 to point C2, so the control rods 5 are withdrawn so that the number of inserted outermost control rods 5 located at the outermost circumference of the reactor core 2 is greater than before at point C2. , thereby attempting to compensate for the reactivity due to the lack of xenone. Further, at that time, the number of inserted outermost control rods 5 at point C2 is determined as follows. That is, as shown in FIG. 8, the outermost circumference control rods 5 located at the outermost circumference are indicated by symbols a, b, c, and d, respectively. here a
There are four outermost control rods 5 indicated by b, eight outermost control rods 5 indicated by C, eight outermost control rods 5 indicated by d, and four outermost control rods 5 indicated by d. . Then, the number of outermost control rods 5 indicated by a, b, c, and d is determined by appropriately combining them in accordance with the relative xenone concentration. Figure 9 shows the number of outermost control rods 5 that are finally inserted at point C2 on the horizontal axis and the relative xenone concentration on the vertical axis, and the relative xenone concentration and the outermost control rods that are finally inserted at point C2. It is a figure showing the relationship with the number of 5. For example, if the xenone concentration at point C2 is expected to be e, the control rod should be adjusted so that the outermost control rod 5 is finally inserted at point C2, as shown by a in FIG. Perform the extraction operation in step 5. Further, when the xenone concentration at point C2 is expected to be f, the control rod 5 is withdrawn so that the outermost control rod 5 shown by b in FIG. 8 is finally in the inserted state. Similarly, when the xenone concentrations are g, h, i, and j, the number of the outermost control rods 5 in the final inserted state is determined in the same way. In this example, the case where the xenone concentration is i is assumed. Therefore, the outermost control rods 5 corresponding to positions a, b, and c in FIG. 7 are inserted. At this time, of course, the control rod operation must be such that the PCIOMR standard can be complied with. Next, since Zenon is gradually accumulated from point C2 onwards, a margin is generated based on the PCIOMR standard, and the outermost control rod 5 that is in the inserted state is gradually pulled out and the target control rod shown in FIG. Aim to increase the output as a pattern. The amount by which the control rod 5 is withdrawn at that time is as follows. In other words, if the control rod 5 is divided into 24 parts in the axial direction, and the axial distance corresponding to one division is taken as the minimum control rod drive unit, then 3 parts per hour will be generated.
Pull out the smallest control rod drive unit one by one. This operation is also intended to increase the output while ensuring compliance with the above PCIOMR standards. Then, by operating the control rods in this manner, the output is increased to point E2 in FIG. After point E2, the output is increased to point G2 via point F2 by adjusting the core flow rate to obtain the rated output state.
以上本実施例による運転方法によると従来のよ
うに一旦上昇させた出力を降下させてあらためて
制御棒操作により出力を上昇させるという操作が
不要となるので操作が簡略化されるとともに定格
出力状態を得るまでに要する時間を短縮させるこ
とができる。これを第3図と第6図との比較で説
明すると従来2日と数時間で略65%程度の出力を
得ていたのに対して、本実施例の場合には2日と
数時間で略80%程度の出力を得ることができ、ま
たその後略3日で定格の出力状態を得ることがで
きる。これは従来略4日を要していたのに対して
略1日の短縮を図ることが可能となる。そしてこ
のように定格出力状態を得るに要する時間の短縮
はプラントの稼動率の向上を図る上で極めて効果
的なことである。また第6図中C2点では炉心2
の中心部近傍の制御棒パターンは目標制御棒パタ
ーンと一致しており、よつてC2点からE2点へ
の出力上昇の際にはそれらの制御棒5を操作する
必要はない。中心部の制御棒5の操作は炉心出力
にあたえる影響が大きく、したがつてこれら中心
部の制御棒5を操作しないということは
PCIOMR基準を遵守する上で極めて効果的なこ
とである。なお前記実施例はゼノンが全く無い状
態を想定して説明したがこれに限つたことではな
く、ゼノンがある程度存在する場合等その状況に
応じて最外周制御棒5の本数を決定して運転すれ
ばよい。 As described above, according to the operating method according to this embodiment, there is no need for the conventional operation of once increasing the output, lowering it, and then increasing the output again by operating the control rods, so the operation is simplified and the rated output state is obtained. The time required for this can be shortened. This can be explained by comparing Figures 3 and 6. Conventionally, approximately 65% of the output was obtained in two days and a few hours, whereas in the case of this example, it took two days and a few hours. Approximately 80% output can be obtained, and the rated output state can be obtained in approximately 3 days thereafter. This conventionally required approximately 4 days, but this can be reduced to approximately 1 day. Shortening the time required to obtain the rated output state in this way is extremely effective in improving the operating rate of the plant. In addition, at point C2 in Figure 6, the core 2
The control rod pattern near the center matches the target control rod pattern, so there is no need to operate those control rods 5 when increasing the output from point C2 to point E2. The operation of the control rods 5 in the center has a large effect on the core output, so not operating the control rods 5 in the center means
This is extremely effective in complying with the PCIOMR standards. Although the above embodiment has been explained assuming a situation where there is no Zenon at all, the present invention is not limited to this, but the number of outermost control rods 5 may be determined and operated according to the situation, such as when a certain amount of Zenon is present. Bye.
〔発明の効果〕
以上詳述したように本発明によれば、炉心から
所定の制御棒を引抜いて原子炉の起動運転を行う
際に、前記炉心の最外周に位置する最外周制御棒
の引抜き本数を相対ゼノン濃度に応じて決定し、
前記相対ゼノン濃度が低い時には前記最外周制御
棒の引抜き本数を少なくして起動運転を行い、そ
の後前記炉心に挿入されている最外周制御棒を
徐々に引抜くことにより、従来のように炉心出力
がPCエンベロープを越えないように炉心流量を
調整しながら起動運転を行う必要がないので、起
動から定格出力運転に至るまでの時間を短縮する
ことができ、目標とする出力レベルに短時間で到
達させることのできる沸騰水型原子炉の運転方法
を提供できる。[Effects of the Invention] As described in detail above, according to the present invention, when a predetermined control rod is pulled out from the core and a reactor is started up, the outermost control rod located at the outermost periphery of the core is pulled out. The number of bottles is determined according to the relative xenone concentration,
When the relative xenone concentration is low, startup operation is performed by reducing the number of outermost control rods that are pulled out, and then the outermost control rods inserted into the reactor core are gradually pulled out to maintain the core output as before. Since there is no need to perform startup operation while adjusting the core flow rate so that the reactor does not exceed the PC envelope, the time from startup to rated power operation can be shortened, and the target output level can be reached in a short time. It is possible to provide a method for operating a boiling water reactor that allows
第1図乃至第5図は従来例を示す図で第1図は
沸騰水型原子炉の概略構成を示す縦断面図、第2
図は炉心の一部平面図、第3図は炉心出力の時間
変化を示す線図、第4図および第5図は制御棒パ
ターンを示す炉心の模式的な平面図、第6図乃至
第9図は本発明の一実施例を示す図で、第6図は
炉心出力の時間変化を示す線図、第7図および第
8図は制御棒パターンを示す炉心の模式的な平面
図、第9図は相対ゼノン濃度と挿入される最外周
制御棒の本数との関係を示す線図である。
2……炉心、4……燃料集合体、5……制御
棒、21……単位格子。
Figures 1 to 5 are diagrams showing conventional examples. Figure 1 is a vertical sectional view showing the schematic configuration of a boiling water reactor, and Figure 2
The figure is a partial plan view of the reactor core, FIG. 3 is a line diagram showing changes in core power over time, FIGS. 4 and 5 are schematic plan views of the core showing control rod patterns, and FIGS. 6 to 9 The figures are diagrams showing one embodiment of the present invention, in which Fig. 6 is a diagram showing temporal changes in core output, Figs. 7 and 8 are schematic plan views of the reactor core showing control rod patterns, and Fig. 9 The figure is a diagram showing the relationship between the relative xenone concentration and the number of outermost control rods inserted. 2...Reactor core, 4...Fuel assembly, 5...Control rod, 21...Unit cell.
Claims (1)
動運転を行う際に、前記炉心の最外周に位置する
最外周制御棒の引抜き本数を相対ゼノン濃度に応
じて決定し、前記相対ゼノン濃度が低い時には前
記最外周制御棒の引抜き本数を少なくして起動運
転を行い、その後前記炉心に挿入されている最外
周制御棒を徐々に引抜き目標制御棒パターンとす
ることを特徴とする沸騰水型原子炉の運転方法。1. When a predetermined control rod is pulled out from the reactor core to perform startup operation of the reactor, the number of the outermost control rods located at the outermost periphery of the core to be pulled out is determined according to the relative xenone concentration, and the relative xenone concentration is When the temperature is low, a startup operation is performed by reducing the number of the outermost control rods to be pulled out, and then the outermost control rods inserted into the reactor core are gradually pulled out to form a target control rod pattern. How to operate a furnace.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59079651A JPS60224093A (en) | 1984-04-20 | 1984-04-20 | Method of operating boiling water type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59079651A JPS60224093A (en) | 1984-04-20 | 1984-04-20 | Method of operating boiling water type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60224093A JPS60224093A (en) | 1985-11-08 |
| JPH053556B2 true JPH053556B2 (en) | 1993-01-18 |
Family
ID=13696026
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59079651A Granted JPS60224093A (en) | 1984-04-20 | 1984-04-20 | Method of operating boiling water type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60224093A (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS52112097A (en) * | 1976-03-15 | 1977-09-20 | Hitachi Ltd | Operating method of reactor |
| JPS56124087A (en) * | 1980-03-05 | 1981-09-29 | Hitachi Ltd | Operating method of bwr type reactor |
-
1984
- 1984-04-20 JP JP59079651A patent/JPS60224093A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60224093A (en) | 1985-11-08 |
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