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JPH0128358B2 - - Google Patents
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JPH0128358B2 - - Google Patents

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Publication number
JPH0128358B2
JPH0128358B2 JP55140006A JP14000680A JPH0128358B2 JP H0128358 B2 JPH0128358 B2 JP H0128358B2 JP 55140006 A JP55140006 A JP 55140006A JP 14000680 A JP14000680 A JP 14000680A JP H0128358 B2 JPH0128358 B2 JP H0128358B2
Authority
JP
Japan
Prior art keywords
control rod
neutron detectors
neutron
belonging
stage
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
Application number
JP55140006A
Other languages
Japanese (ja)
Other versions
JPS5764198A (en
Inventor
Atsuko Suzuki
Shinichiro Tatemichi
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP55140006A priority Critical patent/JPS5764198A/en
Publication of JPS5764198A publication Critical patent/JPS5764198A/en
Publication of JPH0128358B2 publication Critical patent/JPH0128358B2/ja
Granted 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は沸騰水形原子炉等における制御棒の引
抜監視装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod withdrawal monitoring device in a boiling water nuclear reactor or the like.

一般にたとえば沸騰水形原子炉では制御棒の周
囲に中性子検出器を設け、制御棒の引抜の際にこ
の制御棒周囲の局部的な出力上昇を検出し、過度
の出力上昇が生じた場合には制御棒の引抜きを阻
止し、燃料破損を防止して燃料の健全性を維持す
るように構成されている。そして、従来この種の
装置における中性子検出器の配置は第1図に示す
如く格子上に配列された制御棒A……間に2本お
きに中性子検出器B1……,B2……を配置し、4
本の制御棒A……が16個の中性子検出器B1……,
B2……で囲まれるように構成されている。そし
て、これら中性子検出器B1……,B2……は制御
棒A……の軸方すなわち引抜方向と直交する平面
内に配置され、かつこれらが制御棒A……の軸方
向に4段設けられている。そして、上記の中性子
検出器B1……,B2……は2つの系に分けられ一
方の系に属する中性子検出器B1……と他方の群
に属する中性子検出器B2……はそれぞれ互に独
立した2系統の信号処理回路(図示せず)に接続
され、これらの信号処理回路はそれぞれの系の中
性子検出器B1……,B2……からの信号の平均値
を出力するように構成され、いずれかの系の出力
のうちレベルの高い方が設定値に達すると制御棒
の引抜阻止信号が発生されいずれか一方の系が故
障しても、他方の系が作動し、信頼性を高めるよ
うに構成されている。そして、従来これらの中性
子検出器B1……,B2の配置は最下段では一方の
系に属する中性子検出器B1……(図中白丸で示
す)のみを配置し、次の段では他方の系に属する
中性子検出器B2……(図中黒丸で示す)のみを
配置し、その次の段には一方の系に属する中性子
検出器B1……のみを、最上段には他方の系に属
する中性子検出器B2……のみを配置していた。
しかし、炉心の出力分布は制御棒A……の軸方向
について一様ではなく、このため上記の如き中性
子検出器B1……,B2……の配置では制御棒A…
…の引抜量に対する各系の出力レベルすなわち応
答特性に大きな差が生じてしまう。したがつて応
答特性の悪い方の系が故障した場合には問題は生
じないが、応答特性の良い方の系が故障してバイ
パスされたときには制御棒引抜監視装置全体とし
ての応答特性が悪くなつてしまう。したがつて一
方の系がバイパスされているか否かによつて全体
の応答特性が異なつてしまうことになり、制御棒
引抜監視装置全体の安定性が悪く、信頼性が低下
する不具合があつた。
Generally, for example, in a boiling water reactor, a neutron detector is installed around the control rod, and when the control rod is withdrawn, it detects a local increase in power around the control rod, and if an excessive increase in power occurs, it detects a neutron detector. It is configured to prevent control rod withdrawal, prevent fuel damage, and maintain fuel integrity. Conventionally, the arrangement of neutron detectors in this type of device is as shown in Fig. 1, in which control rods A are arranged on a grid, with neutron detectors B 1 , B 2 , and so on every second between them. Place, 4
Book control rod A...... has 16 neutron detectors B 1 ...,
It is structured so that it is surrounded by B 2 .... These neutron detectors B 1 ..., B 2 ... are arranged in a plane perpendicular to the axial direction of the control rod A, that is, the drawing direction, and these neutron detectors B 1 ..., B 2 ... are arranged in four stages in the axial direction of the control rod A ... It is provided. The above neutron detectors B 1 ..., B 2 ... are divided into two systems, with the neutron detector B 1 ... belonging to one system and the neutron detector B 2 ... belonging to the other group, respectively. It is connected to two mutually independent signal processing circuits (not shown), and these signal processing circuits output the average value of the signals from the neutron detectors B 1 ..., B 2 ... of each system. When the higher level output of either system reaches the set value, a control rod withdrawal prevention signal is generated, and even if either system fails, the other system is activated. Constructed to increase reliability. Conventionally, the arrangement of these neutron detectors B 1 ..., B 2 is such that only the neutron detector B 1 ... (indicated by a white circle in the figure) belonging to one system is arranged at the bottom stage, and the other one is arranged at the next stage. Only the neutron detector B 2 ... (indicated by a black circle in the figure) belonging to the system is placed in the next stage, and only the neutron detector B 1 ... belonging to one system is placed in the next stage, and the other neutron detector B 1 ... is placed in the top stage. Only the neutron detector B 2 belonging to the system was placed.
However, the power distribution in the reactor core is not uniform in the axial direction of the control rods A..., and for this reason, in the arrangement of the neutron detectors B 1 ..., B 2 ... as described above, the control rods A...
A large difference occurs in the output level, that is, the response characteristics of each system with respect to the amount of withdrawal. Therefore, if the system with worse response characteristics fails, no problem will occur, but if the system with better response characteristics fails and is bypassed, the response characteristics of the control rod withdrawal monitoring system as a whole will deteriorate. I end up. Therefore, the overall response characteristics differ depending on whether one system is bypassed or not, resulting in poor stability of the control rod withdrawal monitoring system as a whole, resulting in a reduction in reliability.

本発明は以上の事情にもとづいてなされたもの
で、その目的とするところは独立した複数の系統
の系を有するものにおいて、各系の特性が均一で
あつていずれかの系がバイパスされた場合でも全
体の特性に大きな変化がなく、作動が安定し信頼
性の高い原子炉の制御棒引抜監視装置を得ること
にある。
The present invention has been made based on the above-mentioned circumstances, and its purpose is to provide a system having a plurality of independent systems, where the characteristics of each system are uniform and one of the systems is bypassed. However, the objective is to obtain a control rod withdrawal monitoring device for a nuclear reactor that has stable operation and high reliability without major changes in overall characteristics.

以下本発明を図面に示す実施例にしたがつて説
明する。第2図は本発明の第1実施例を示す。こ
の第1実施例は本発明を沸騰水形原子炉の制御棒
引抜監視装置に適用したものであつて、図中1…
…は制御棒であつて断面十字形をなしている。そ
してこれらは制御棒1……の周囲には4個の燃料
集合体(図示せず)がそれぞれ配置されて単位格
子を形成し、これら単位格子が格子状に配列され
て炉心を構成している。そしてこれら単位格子間
には単位格子2個おきすなわち制御棒1……2本
おきに中性子検出器2……,3……,4……,5
……、が格子状に配置されている。したがつて第
2図に示す如く4個の単位格子すなわち4本の制
御棒1……は16個の中性子検出器2……,3…
…,4……,5……、で囲まれている。これら16
個の中性子検出器2……,3……,4……,5…
…は水平面すなわち制御棒1……の軸方向と直交
する面に沿つて配置されており、またこれらは制
御棒1……の軸方向に沿つて等間隔に4段設けら
れている。したがつて4本の制御棒1……は4個
4段合計16個の中性子検出器2……,3……,4
……,5……によつて囲まれている。そしてこれ
ら中性子検出器2……,3……,4……,5……
は各段に設けられている中性子検出器数と等しい
群数すなわち4個ずつ4群に分けられ、各群のも
のは各群毎にそれぞれに互に独立して設けられた
信号処理回路(図示せず)に接続され互に独立し
た4系統の系に分けられている。なお第2図中第
1の系に属する中性子検出器2……は黒丸で、第
2の系に属する中性子検出器3……は白丸で、第
3の系に属する中性子検出器4……は黒三角で、
また第4の系に属する中性子検出器5……は白三
角で示す。そして、各系の信号処理回路では各系
に属する中性子検出器2……,3……,4……,
5……からの信号の平均値を出力信号とし、各系
の出力信号のうちの最も高いものが所定の設定値
に達した場合には制御棒1……の引抜を阻止する
ブロツク信号を発生するように構成され、またい
ずれかの系が故障した場合にはその系がバイパス
され、残りの系が作動するように構成されてい
る。そして、上記中性子検出器2……,3……,
4……,5……は各段において各系に属する中性
子検出器2……,3……,4……,5……が1個
ずつ配置されている。またこれら中性子検出器2
……,3……,4……,5……は最下段において
は第2図中右上側に第1の系に属する中性子検出
器2……が配置され、以下第2、第3、第4の系
に属する中性子検出器3……,4……,5……の
順に上方から見て反時計回りに配置され、また次
の段においては右下側に第1の系に属する中性子
検出器2……が配置され以下第2、第3、第4の
系に属する中性子検出器3……,4……,5……
の順に上方から見て反時計回りに配置されると云
つた様に各段において各系に属する中性子検出器
2……,3……,4……,5……が順次90゜ずつ
ずれて配置されている。なお、第2図には4本の
制御棒1……とこれを囲む中性子検出器2……,
3……,4……,5……のみを記したが、実際に
は制御棒1……とその周囲に配置された燃料集合
体からなる単位格子は多数配列されており、した
がつて各中性子検出器2……,3……,4……,
5……は隣接する4本の制御棒の監視用としても
兼用されるものであり、ある制御棒1……を引抜
く場合にはその制御棒1……を囲む4個4段合計
16個の中性子検出器2……,3……,4……,5
……がその制御棒1……の引抜監視用として自動
選択装置(図示せず)により選択され作動するも
のである。
The present invention will be described below with reference to embodiments shown in the drawings. FIG. 2 shows a first embodiment of the invention. In this first embodiment, the present invention is applied to a control rod withdrawal monitoring device for a boiling water reactor, and in the figure, 1...
... is a control rod and has a cross-shaped cross section. Four fuel assemblies (not shown) are arranged around each of the control rods 1 to form a unit cell, and these unit cells are arranged in a lattice to form the reactor core. . And between these unit cells, there are every two unit cells, that is, control rods 1... every two neutron detectors 2..., 3..., 4..., 5.
...are arranged in a grid pattern. Therefore, as shown in Fig. 2, four unit cells, that is, four control rods 1..., have 16 neutron detectors 2..., 3...
It is surrounded by..., 4..., 5.... these 16
neutron detectors 2..., 3..., 4..., 5...
... are arranged along a horizontal plane, that is, a plane perpendicular to the axial direction of the control rods 1 ..., and these are provided in four stages at equal intervals along the axial direction of the control rods 1 .... Therefore, the four control rods 1... have 4 4-stage neutron detectors, totaling 16 neutron detectors 2..., 3..., 4
It is surrounded by ..., 5.... And these neutron detectors 2..., 3..., 4..., 5...
The number of groups is equal to the number of neutron detectors provided in each stage, that is, it is divided into 4 groups of 4, and each group has a signal processing circuit provided independently for each group (Fig. (not shown) and is divided into four independent systems. In Figure 2, neutron detector 2... belonging to the first system is a black circle, neutron detector 3... belonging to the second system is a white circle, and neutron detector 4... belonging to the third system is a black circle. black triangle,
Further, the neutron detectors 5 belonging to the fourth system are indicated by white triangles. In the signal processing circuit of each system, the neutron detectors 2..., 3..., 4..., belonging to each system,
The average value of the signals from 5... is used as the output signal, and when the highest output signal of each system reaches a predetermined set value, a block signal is generated to prevent the withdrawal of control rod 1... If any system fails, that system is bypassed and the remaining systems are activated. And the neutron detectors 2..., 3...,
4..., 5..., one neutron detector 2..., 3..., 4..., 5... belonging to each system is arranged in each stage. Also, these neutron detectors 2
......, 3..., 4..., 5..., the neutron detector 2... belonging to the first system is arranged on the upper right side in Fig. 2 in the bottom row, and the neutron detectors 2... belong to the first system, and the neutron detectors 2... Neutron detectors 3..., 4..., 5... belonging to system 4 are arranged counterclockwise when viewed from above, and in the next stage, neutron detectors belonging to system 1 are placed on the lower right side. neutron detectors 3..., 4..., 5... belonging to the second, third, and fourth systems.
In each stage, the neutron detectors 2..., 3..., 4..., 5... belonging to each system are arranged in order counterclockwise when viewed from above, and are shifted by 90 degrees in sequence. It is located. In addition, Fig. 2 shows four control rods 1 and surrounding neutron detectors 2,
Although only 3..., 4..., 5... are shown, in reality, a large number of unit cells consisting of the control rod 1... and the fuel assemblies arranged around it are arranged, so each Neutron detector 2..., 3..., 4...,
5... is also used for monitoring the four adjacent control rods, and when a certain control rod 1... is pulled out, a total of 4 pieces surrounding that control rod 1... in 4 stages are used.
16 neutron detectors 2..., 3..., 4..., 5
. . . is selected and activated by an automatic selection device (not shown) for monitoring the withdrawal of the control rod 1 .

以上の如く構成された本発明の第1実施例は、
制御棒1……の引抜による局部的な出力上昇すな
わち中性子束の増加を中性子検出器2……,3…
…,4……,5……で検出し、その値が設定値に
達した場合にはブロツク信号が発生されて制御棒
1……の引抜を阻止し、燃料の健全性が維持され
る。そしてこのものは、各系に属する中性子検出
器2……,3……,4……,5……が各段に1個
ずつ配置されているので、監視すべき制御棒1…
…の周囲の軸方向の出力分布の不均一さの影響が
従来の場合に比較して全ての系に等しく影響し、
したがつて制御棒1の引抜量に対する各系の出力
レベルすなわち応答特性が等しくなり、各系の応
答特性の差がきわめて少なくなる。よつてたとえ
ば応答特性の最も良い系が故障してバイパスされ
た場合でも制御棒引抜監視装置全体としての応答
特性にはほとんど変化を生じないので全体として
の作動は安定し信頼性が向上する。また、この第
1実施例は段数が各段に配置されている4個中性
子検出器2……,3……,4……,5……の個数
に等しい4段であり、かつ各段においては各系の
中性子検出器2……,3……,4……,5……の
配置が90゜ずつずれているため、各系における4
個の中性子検出器2……,3……,4……,5…
…は制御棒1……の軸方向と直交する面内におけ
る異なつた位置にそれぞれ1個ずつ配置されるの
で、制御棒1……の軸方向と直交する方向の出力
分布の不均一さも各系に均等に影響し、各系の特
性をより等しくできる。なお第3図にはこの効果
を確認するためにおこなつた試験の結果を示す。
第3図中破線Cは第1図に示す従来のものにおい
て応答特性の良い方の系が故障した場合の応答特
性であり、また実線Dは上記第1実施例のものに
おいて最も応答特性の良い系が故障した場合の応
答特性を示す。この結果から明らかなように従来
のものは制御棒引抜位置Eで設定レベルLに達す
るものであるが、この第1実施例のものはこれよ
り小さな制御棒引抜位置下で設定レベルLの信号
が出力され、より早い位置で制御棒1……をブロ
ツクできる。
The first embodiment of the present invention configured as described above is as follows:
Neutron detectors 2..., 3... detect the local increase in output, that is, the increase in neutron flux due to the withdrawal of control rods 1...
. . , 4 . . . , 5 . In this case, neutron detectors 2..., 3..., 4..., 5... belonging to each system are arranged one at each stage, so the control rod 1 to be monitored...
The influence of the non-uniformity of the axial power distribution around ... affects all systems equally compared to the conventional case,
Therefore, the output level, that is, the response characteristics of each system with respect to the amount of control rod 1 withdrawn becomes equal, and the difference in response characteristics of each system becomes extremely small. Therefore, even if, for example, the system with the best response characteristics fails and is bypassed, there will be little change in the response characteristics of the control rod withdrawal monitoring system as a whole, and the overall operation will be stable and reliability will be improved. Further, in this first embodiment, the number of stages is four, which is equal to the number of four neutron detectors 2..., 3..., 4..., 5... arranged in each stage, and in each stage, Because the arrangement of neutron detectors 2..., 3..., 4..., 5... in each system is shifted by 90 degrees,
neutron detectors 2..., 3..., 4..., 5...
... are placed at different positions in the plane orthogonal to the axial direction of control rod 1..., so the non-uniformity of the output distribution in the direction orthogonal to the axial direction of control rod 1... , and the characteristics of each system can be made more equal. Furthermore, Fig. 3 shows the results of a test conducted to confirm this effect.
The broken line C in FIG. 3 is the response characteristic when the system with the better response characteristic fails in the conventional system shown in FIG. This shows the response characteristics when the system fails. As is clear from this result, the conventional signal reaches the set level L at the control rod withdrawal position E, but the signal of the first embodiment reaches the set level L at a smaller control rod withdrawal position. It is possible to block the control rod 1 at an earlier position.

以上詳述したように本発明による原子炉の制御
棒引抜監視装置は、監視すべき制御棒を囲んでこ
の制御棒と直交する面に沿つて配置されたn個の
中性子検出器を上記制御棒の軸方向に沿つてn段
設け、上記中性子検出器からの信号を処理する信
号処理回路を互いに独立したn個の系に分け、上
記各段に配置されたn個の中性子検出器をそれぞ
れ1個ずつ異なる系の上記信号処理回路に属する
ようにし、かつ任意の1個の前記信号処理回路に
属する中性子検出器は各段毎に異なる位置に配置
されていることを特徴とするものである。したが
つて監視すべき制御棒周囲の出力分布の不均一さ
が全部の系に等しく影響し、各系の応答特性の差
がきわめて少なくなる。したがつて応答特性の最
も良い系が故障してバイパスされたような場合で
も装置全体としての応答特性の変化がきわめて少
なく、作動が安定し信頼性が向上する。さらに本
発明の場合には、各信号処理回路系において中性
子検出器の水平方向配置分布が等しい構成となつ
ているので、水平方向の出力分布の不均一さに起
因する各系の特性の差異をも効果的に解消するこ
とができ、信頼性をより向上させることができ
る。
As described in detail above, the control rod withdrawal monitoring device for a nuclear reactor according to the present invention includes n neutron detectors that surround the control rod to be monitored and are arranged along a plane orthogonal to the control rod. n stages are provided along the axis direction, the signal processing circuit for processing the signal from the neutron detector is divided into n mutually independent systems, and each of the n neutron detectors arranged in each stage is divided into one The neutron detectors are arranged to belong to the signal processing circuits of different systems, and the neutron detectors belonging to any one of the signal processing circuits are arranged at different positions for each stage. Therefore, non-uniformity in the power distribution around the control rods to be monitored affects all systems equally, and the differences in response characteristics of each system are extremely small. Therefore, even if the system with the best response characteristics fails and is bypassed, there is very little change in the response characteristics of the device as a whole, resulting in stable operation and improved reliability. Furthermore, in the case of the present invention, since the horizontal distribution of the neutron detectors in each signal processing circuit system is the same, differences in the characteristics of each system due to non-uniformity of the horizontal output distribution can be eliminated. can also be effectively eliminated, and reliability can be further improved.

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

第1図は従来例の要部を模式的に示す斜視図で
ある。第2図は本発明の第1実施例の要部を模式
的に示す斜視図、第3図は第1実施例と従来例の
故障時における応答特性を示す特性図である。 1……制御棒、2……第1の系に属する中性子
検出器、3……第2の系に属する中性子検出器、
4……第3の系に属する中性子検出器、5……第
4の系に属する中性子検出器。
FIG. 1 is a perspective view schematically showing the main parts of a conventional example. FIG. 2 is a perspective view schematically showing the main parts of the first embodiment of the present invention, and FIG. 3 is a characteristic diagram showing the response characteristics of the first embodiment and the conventional example at the time of failure. 1... Control rod, 2... Neutron detector belonging to the first system, 3... Neutron detector belonging to the second system,
4...A neutron detector belonging to the third system, 5...A neutron detector belonging to the fourth system.

Claims (1)

【特許請求の範囲】[Claims] 1 監視すべき制御棒を囲んでこの制御棒と直交
する面に沿つて配置されたn個の中性子検出器を
上記制御棒の軸方向に沿つてn段設け、上記中性
子検出器からの信号を処理する信号処理回路を互
いに独立したn個の系に分け、上記各段に配置さ
れたn個の中性子検出器をそれぞれ1個ずつ異な
る系の上記信号処理回路に属するようにし、かつ
任意の1個の前記信号処理回路系に属する中性子
検出器は各段毎に異なる位置に配置されているこ
とを特徴とする制御棒引抜監視装置。
1 N neutron detectors are arranged in n stages along the axial direction of the control rod, surrounding the control rod to be monitored and arranged along a plane orthogonal to the control rod, and the signals from the neutron detectors are The signal processing circuit to be processed is divided into n mutually independent systems, and each of the n neutron detectors arranged in each stage is made to belong to the signal processing circuit of a different system, and any one A control rod withdrawal monitoring device characterized in that neutron detectors belonging to each of the signal processing circuit systems are arranged at different positions for each stage.
JP55140006A 1980-10-07 1980-10-07 Device for monitoring withdrawal of nuclear control rod Granted JPS5764198A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55140006A JPS5764198A (en) 1980-10-07 1980-10-07 Device for monitoring withdrawal of nuclear control rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55140006A JPS5764198A (en) 1980-10-07 1980-10-07 Device for monitoring withdrawal of nuclear control rod

Publications (2)

Publication Number Publication Date
JPS5764198A JPS5764198A (en) 1982-04-19
JPH0128358B2 true JPH0128358B2 (en) 1989-06-02

Family

ID=15258732

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55140006A Granted JPS5764198A (en) 1980-10-07 1980-10-07 Device for monitoring withdrawal of nuclear control rod

Country Status (1)

Country Link
JP (1) JPS5764198A (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5364190A (en) * 1976-11-17 1978-06-08 Toshiba Corp Observation device of the prevention of control rod extracting

Also Published As

Publication number Publication date
JPS5764198A (en) 1982-04-19

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