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JPH0634080B2 - Refueling machine with built-in control rod drive mechanism - Google Patents
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JPH0634080B2 - Refueling machine with built-in control rod drive mechanism - Google Patents

Refueling machine with built-in control rod drive mechanism

Info

Publication number
JPH0634080B2
JPH0634080B2 JP61068650A JP6865086A JPH0634080B2 JP H0634080 B2 JPH0634080 B2 JP H0634080B2 JP 61068650 A JP61068650 A JP 61068650A JP 6865086 A JP6865086 A JP 6865086A JP H0634080 B2 JPH0634080 B2 JP H0634080B2
Authority
JP
Japan
Prior art keywords
fuel
control rod
core
drive mechanism
gripper
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
Application number
JP61068650A
Other languages
Japanese (ja)
Other versions
JPS62226097A (en
Inventor
俊幸 鈴木
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 JP61068650A priority Critical patent/JPH0634080B2/en
Publication of JPS62226097A publication Critical patent/JPS62226097A/en
Publication of JPH0634080B2 publication Critical patent/JPH0634080B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
  • Control Of Throttle Valves Provided In The Intake System Or In The Exhaust System (AREA)
  • Load-Engaging Elements For Cranes (AREA)
  • Fuel-Injection Apparatus (AREA)

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は高速炉において制御棒の駆動と燃料交換を行う
制御棒駆動機構内蔵燃料交換機に関する。
DETAILED DESCRIPTION OF THE INVENTION Object of the Invention (Field of Industrial Application) The present invention relates to a fuel exchanger with a control rod drive mechanism for driving control rods and exchanging fuel in a fast reactor.

(従来の技術) 高速炉にはループ型とタンク型とがあるが、いずれの型
においても原子炉容器内の燃料を取扱うために燃料交換
機が原子炉容器の上方を閉塞する遮蔽プラグ上に設置さ
れている。
(Prior Art) There are two types of fast reactors, a loop type and a tank type. In both types, the fuel exchanger is installed on the shield plug that closes the upper part of the reactor vessel to handle the fuel in the reactor vessel. Has been done.

また、炉心の上方には、制御棒駆動機構等を保持する炉
心上部機構が設けられ、燃料を原子炉容器内で交換する
ため、炉心上部機構と燃料交換装置を回転プラグ内に配
置し、回転プラグの回転動作や燃料交換装置の旋回動作
で燃料交換装置が炉心のすべての領域にアクセスできる
ようにしている。
An upper core mechanism that holds the control rod drive mechanism etc. is installed above the core.To exchange fuel in the reactor vessel, the upper core mechanism and the fuel exchange device are placed in a rotating plug to The rotating movement of the plug and the swiveling movement of the refueling device allow the refueling device to access all regions of the core.

上記の燃料交換装置は、グリッパ昇降、燃料の掴み・放
しの機能のほか、燃料引抜き時に周囲の燃料の浮き上が
りを防止するため、周囲燃料をホールドダウンする機構
を備えており、長尺、大重量の機器を構成している。
In addition to the functions of lifting and lowering the gripper, grasping and releasing the fuel, the above fuel exchange device is equipped with a mechanism for holding down the surrounding fuel to prevent the surrounding fuel from rising when the fuel is withdrawn. The equipment of.

(発明が解決しようとする問題点) 以上のように、従来の原子炉では遮蔽プラグ上に専用機
としての燃料交換装置を設けており、構造が複雑で物量
的にも配置スペース的にも原子炉構造の中で大きな比重
を占めていた。
(Problems to be Solved by the Invention) As described above, in the conventional nuclear reactor, the fuel exchange device as a dedicated machine is provided on the shielding plug, and the structure is complicated, and the atomization is possible in terms of physical quantity and arrangement space. It had a large specific gravity in the furnace structure.

本発明はかかる点に鑑みてなされたものであり、原子炉
および燃料交換設備の簡易化を計るため、燃料交換を取
扱う燃料交換装置を削除し、制御棒駆動機構のグリッパ
で制御棒の他、燃料も取扱できるようにし、また、回転
プラグの持上げ、持下げ動作でホールドダウンを行うこ
とによって燃料交換装置のホールドダウン装置をも削除
した制御棒駆動機構内蔵燃料交換機を提供することを目
的とするものである。
The present invention has been made in view of the above points, in order to simplify the reactor and fuel exchange equipment, the fuel exchange device that handles the fuel exchange is deleted, in addition to the control rods with the gripper of the control rod drive mechanism, An object of the present invention is to provide a fuel exchanger with a built-in control rod drive mechanism that enables handling of fuel and that also removes the hold-down device of the fuel exchange device by holding down the rotary plug by lifting and lowering the rotary plug. It is a thing.

[発明の構成] (問題点を解決するための手段) 本発明は、制御棒上方の炉心上部機構内に設置され、制
御棒の掴みおよび放し、引抜き、スクラム機能と、燃料
の掴みおよび放し、挿入、引抜き機能とを備えた制御棒
駆動機構内蔵燃料交換機において、この制御棒駆動機構
内蔵燃料交換機は、炉心の内側領域のみを取扱う内側燃
料交換装置と、炉心の外側領域のみを取扱う外側燃料交
換装置とから成ることを特徴とする。
[Structure of the Invention] (Means for Solving Problems) The present invention is installed in a core upper mechanism above a control rod, and grasps and releases the control rod, withdraws, scrums, and grasps and releases fuel. In a fuel exchange machine with a control rod drive mechanism equipped with insertion and extraction functions, this fuel exchange machine with a control rod drive mechanism has an inner fuel exchange device that handles only the inner region of the core and an outer fuel exchange that handles only the outer region of the core. And a device.

(作用) 上述のように構成した本発明の制御棒駆動機構内蔵燃料
交換機においては、燃料を引抜く際の周囲燃料のホール
ドダウンを回転プラグの旋回用に設置されている回転プ
ラグの持上げ装置で行い、回転プラグの旋回動作で燃料
出入機までの燃料移送を行うようにし、さらに燃料交換
機は、炉心の内側領域のみを取扱うものと、炉心の外側
領域のみを取扱うものとしたので、燃料交換装置を削除
でき、遮蔽プラグ上の機器配置を容易にすることができ
る。
(Operation) In the control rod drive mechanism built-in fuel exchanger of the present invention configured as described above, the rotary plug lifting device installed for turning the rotary plug is used to hold down the surrounding fuel when extracting the fuel. Then, the fuel is transferred to the fuel inlet / outlet unit by the swiveling operation of the rotary plug. Furthermore, the fuel exchange unit handles only the inner region of the core and the outer region of the core. Can be eliminated, and the device arrangement on the shielding plug can be facilitated.

(実施例) 次に、本発明の実施例を図面を参照して説明する。(Example) Next, the Example of this invention is described with reference to drawings.

第1図は本発明を適用した原子炉構造の主要部の構成例
を示すものであり、炉心1を収納した原子炉容器2の上
部には小回転プラグ3、大回転プラグ4を設けた遮蔽プ
ラグ5が設置されており、循環ポンプ6や燃料出入機7
等が搭載されている。また、出力運転時に炉心1上部に
位置する小回転プラグ3には制御棒駆動機構等を保持す
る炉心上部機構8が設けられ、その内には制御棒駆動機
構の機能を兼ねた燃料交換装置9が常設されている。
FIG. 1 shows a structural example of a main part of a nuclear reactor structure to which the present invention is applied, in which a small rotation plug 3 and a large rotation plug 4 are provided above a reactor vessel 2 accommodating a core 1. 5 are installed, and a circulation pump 6 and a fuel exit / entry machine 7 are installed.
Etc. are installed. Further, a core rotating mechanism 8 for holding a control rod driving mechanism and the like is provided in the small rotating plug 3 located above the core 1 during power operation, and a fuel exchange device 9 also having a function of the control rod driving mechanism is provided therein. Is permanently installed.

第2図は、上述した燃料交換装置9の構成例を示すもの
であり、この燃料交換装置は駆動部10および上部案内
管11よりなり、駆動部10の頂部には駆動モータ12
が収容され、二重管構造の駆動軸に連結されており、ネ
ジ状の駆動軸外側13aには駆動モータ12の回転によ
って垂直方向に上下動するボールナット14が螺合され
ている。このボールナット14の下端には電磁石15が
設けられている。符号13bは駆動軸内側を示す。
FIG. 2 shows an example of the configuration of the above-described fuel exchange device 9. This fuel exchange device comprises a drive unit 10 and an upper guide tube 11, and a drive motor 12 is provided on the top of the drive unit 10.
Is connected to a drive shaft having a double pipe structure, and a ball nut 14 that vertically moves up and down by the rotation of the drive motor 12 is screwed onto the screw-shaped drive shaft outer side 13a. An electromagnet 15 is provided at the lower end of the ball nut 14. Reference numeral 13b indicates the inside of the drive shaft.

また、上部案内管11には、炉内冷却材が駆動部10内
に侵入するのを防止するストロークベローズ16、ラッ
チベローズ17を設けた内側延長管18および外側延長
管19が配置されている。さらに、外側延長管19の外
側には、同心的に配置した加速スプリング20を介して
加速管21が設置されている。
Further, the upper guide pipe 11 is provided with a stroke bellows 16 for preventing the in-furnace coolant from entering the drive unit 10, an inner extension pipe 18 provided with a latch bellows 17, and an outer extension pipe 19. Further, on the outside of the outer extension pipe 19, an acceleration pipe 21 is installed via an acceleration spring 20 arranged concentrically.

また内側延長管18の先端にはグリッパ開閉ロッド22
が設けられ、連結リンク23を介して制御棒24および
燃料(制御棒の場合は下部案内管25)を掴むことので
きるグリッパ26に接続されている。そして駆動部には
グリッパ開閉ロッド22を接続した内側延長管18の落
下緩衝部27を上下動するグリッパ開閉駆動機構28が
設置されている。
Further, a gripper opening / closing rod 22 is provided at the tip of the inner extension pipe 18.
Is provided and is connected via a connecting link 23 to a control rod 24 and a gripper 26 capable of gripping the fuel (lower guide pipe 25 in the case of a control rod). Further, a gripper opening / closing drive mechanism 28 for vertically moving a drop buffer portion 27 of the inner extension pipe 18 to which the gripper opening / closing rod 22 is connected is installed in the drive portion.

次に、上記のように構成された本発明装置の作用につい
て説明する。
Next, the operation of the device of the present invention configured as described above will be described.

原子炉の出力運転時には第3図に示すように、グリッパ
26により制御棒24の頂部が外側からつかまれてお
り、グリッパ開閉ロッドを接続した内側延長管18の上
部は、電磁石15を励磁していることにより、この図の
状態に保持され、外側延長管19の上下動により、制御
棒のストローク調整を行っている。
As shown in FIG. 3, during the output operation of the nuclear reactor, the top of the control rod 24 is grasped from the outside by the gripper 26, and the electromagnet 15 is excited by the upper portion of the inner extension pipe 18 to which the gripper opening / closing rod is connected. Thus, the state shown in this figure is maintained, and the stroke of the control rod is adjusted by the vertical movement of the outer extension tube 19.

一方、スクラム動作時において、制御棒24を落下させ
る際には電磁石15を消磁し、内側延長管18のみを落
下緩衝部27まで落下させ、その間、連結リンク23が
グリッパ26を押し開かせるとともに、加速管21下面
が制御棒24の頂部を確実に押し出す。
On the other hand, during the scrum operation, when the control rod 24 is dropped, the electromagnet 15 is demagnetized and only the inner extension pipe 18 is dropped to the drop buffer portion 27, while the connection link 23 pushes the gripper 26 open, and The lower surface of the accelerating tube 21 surely pushes the top of the control rod 24.

また、燃料交換時においては、制御棒24を切離した
後、第4図に示すように落下緩衝部27を吊り下げてグ
リッパをつぼめた状態で、下部案内管25もしくは、同
一のハンドリングヘッド形状をした燃料を掴むために、
炉心までグリッパ部を降下させる。このようにしてグリ
ッパが炉心頂部に到達した後には、第5図に示すように
内側延長管18を保持した落下緩衝部27を下げて連結
リンク23を介してグリッパ26を開かせることによっ
て、燃料30を掴むことができる。
Further, at the time of refueling, after the control rod 24 is cut off, the lower guide pipe 25 or the same handling head shape is used with the drop buffer 27 suspended and the gripper closed as shown in FIG. To grab the fuel
Lower the gripper to the core. After the gripper reaches the core top in this way, as shown in FIG. You can grab 30.

さらに、燃料30を引き抜く場合には、駆動軸13bを
下げてグリッパ26が閉となることを防止しながら、外
側延長管19を上昇させれば燃料30を引抜くことがで
きる。なお、燃料30を挿入する際にには、この逆の手
順をとればよい。
Further, when the fuel 30 is extracted, the fuel 30 can be extracted by raising the outer extension pipe 19 while preventing the gripper 26 from closing by lowering the drive shaft 13b. It should be noted that the reverse procedure may be taken when inserting the fuel 30.

また下部案内管24も同様な手順で取扱うことができ
る。
Further, the lower guide tube 24 can be handled by the same procedure.

そして、第6図に示すように小回転プラグ3上には、内
側燃料交換装置9aと外側燃料交換装置9bの2基が設
置されている。ここで、内側燃料交換装置9aは炉心の
内側領域のみを取扱うものとし、外側燃料交換装置9b
は炉心の外側領域のみを取扱うものとする。炉心の内側
領域から燃料出入機受渡位置31に燃料を移送する場合
には、あらかじめ炉心内中継位置32の燃料を引抜き、
ここを中継点として内側燃料交換装置9aから外側燃料
交換装置9bへ受渡せば良い。この際、取扱う燃料の湾
曲等に対しては、炉心内中継位置32への燃料挿入に支
障が生じないように、その周囲の数本の燃料等もあらか
じめ引抜いておくことで対応できる。
Then, as shown in FIG. 6, on the small rotary plug 3, two units, an inner fuel exchange device 9a and an outer fuel exchange device 9b, are installed. Here, the inner fuel exchange device 9a handles only the inner region of the core, and the outer fuel exchange device 9b
Shall deal only with the outer region of the core. When the fuel is transferred from the inner region of the core to the fuel inlet / outlet delivery position 31, the fuel in the core relay position 32 is extracted beforehand.
It suffices to transfer it from the inner fuel exchange device 9a to the outer fuel exchange device 9b using this as a relay point. At this time, the bending of the fuel to be handled can be dealt with by pulling out several fuels and the like around it in advance so as not to hinder the fuel insertion into the intra-core relay position 32.

なお、回転プラグ3,4を旋回させる時には、持上げ装
置によりジャッキアップするが、炉心から燃料を引抜く
際にはこれをジャッキダウンさせれば、炉心上部機構下
端により引抜き燃料の周囲燃料の浮き上がりを防止でき
る。
When the rotary plugs 3 and 4 are swung, they are jacked up by a lifting device, but when the fuel is extracted from the core, if this is jacked down, the lower end of the core upper mechanism prevents the fuel around the extracted fuel from floating. It can be prevented.

また燃料交換終了後に制御棒24を掴む場合には、第7
図に示すように、グリッパ26が炉心頂部に達した後
に、落下緩衝部27を下げて、連絡リンク23を介し
て、一度グリッパ27を開かせる。そしてさらに、外側
延長管19を降下させ、落下緩衝部27を吊り上げると
制御棒24の頂部をグリッパ26で掴むことができる。
When grasping the control rod 24 after the refueling is finished,
As shown in the figure, after the gripper 26 reaches the core top part, the drop buffer part 27 is lowered to once open the gripper 27 via the communication link 23. Further, when the outer extension pipe 19 is lowered and the drop buffer portion 27 is lifted, the top of the control rod 24 can be gripped by the gripper 26.

なお、上記実施例において、一例としてグリッパを内側
に閉じれば制御棒を掴み、外側に開けば燃料を掴む例に
つき説明したが、本発明はこれに限定されるものではな
く、他の把持方法も同様に適用できる。
In the above embodiment, an example in which the control rod is grasped by closing the gripper inside and the fuel is grasped by opening it outside is explained as an example, but the present invention is not limited to this, and other grasping methods are also possible. The same applies.

[発明の効果] 以上、説明したように本発明によれば、燃料交換のみを
行う燃料交換装置を削除することができ、さらには制御
棒駆動機構機能を有する燃料交換機を炉心の内側領域の
みを取扱う機能のものと、炉心の外側領域のみを取扱う
機能を有するものとに分けることによって、交換機の水
平方向の移動範囲が縮少でき、合わせて小回転プラグ、
大回転プラグ、炉心の各々の径を縮少させることができ
るのでより設備を縮少、簡易化することができる。
[Effects of the Invention] As described above, according to the present invention, it is possible to eliminate the fuel exchange device that only performs the fuel exchange, and further to provide the fuel exchange machine having the control rod drive mechanism function only in the inner region of the core. By dividing into those with the function of handling and those with the function of handling only the outer region of the core, the horizontal movement range of the exchange can be reduced, and in addition, a small rotation plug,
Since the diameters of the large rotation plug and the core can be reduced, the equipment can be reduced and simplified.

また通常、燃料交換時にのみ燃料交換装置を設置するた
め、この準備作業に時間を要するが、本発明によれば炉
停止直後に燃料交換を行うことができ、稼働率が向上す
る。さらに遮蔽プラグ上の搭載荷重も削除でき、設計も
容易となる。
Further, normally, since the refueling device is installed only at the time of refueling, this preparatory work requires time, but according to the present invention, refueling can be performed immediately after the reactor is stopped, and the operating rate is improved. In addition, the load on the shield plug can be eliminated, and the design becomes easier.

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

第1図は本発明の適用例を示す原子炉主要部の概略図、
第2図は本発明の燃料交換機の全体図、第3図から第5
図および第7図はそれぞれ本発明の燃料交換機の作動説
明図、第6図は本発明が適用される原子炉の平面図であ
る。 1……炉心 2……原子炉容器 3……小回転プラグ 4……大回転プラグ 5……遮蔽プラグ 6……循環ポンプ 7……燃料出入機 8……炉心上部機構 9……燃料交換装置 9a……内側燃料交換装置 9b……外側燃料交換装置 10……駆動部 11……上部案内管 12……駆動モータ 13a……駆動軸外側 13b……駆動軸内側 14……ボールナット 15……電磁石 16……ストークベローズ 17……ラッチベローズ 18……内側延長管 19……外側延長管 20……加速スプリング 21……加速管 22……グリッパ開閉ロッド 23……連結リンク 24……制御棒 25……下部案内管 26……グリッパ 27……落下緩衝部 28……グリッパ開閉駆動装置 30……燃料 31……燃料出入機受渡し位置
FIG. 1 is a schematic view of a main part of a nuclear reactor showing an application example of the present invention,
FIG. 2 is an overall view of the fuel exchanger of the present invention, and FIGS.
FIG. 7 and FIG. 7 are operation explanatory views of the fuel exchanger of the present invention, and FIG. 6 is a plan view of a nuclear reactor to which the present invention is applied. 1 ... Reactor 2 ... Reactor Vessel 3 ... Small Rotation Plug 4 ... Large Rotation Plug 5 ... Shielding Plug 6 ... Circulation Pump 7 ... Fuel In / Out 8 ... Reactor Upper Mechanism 9 ... Fuel Exchanger 9a …… Inside fuel exchange device 9b …… Outside fuel exchange device 10 …… Driving part 11 …… Upper guide tube 12 …… Driving motor 13a …… Driving shaft outside 13b …… Driving shaft inside 14 …… Ball nut 15 …… Electromagnet 16 …… Stoke bellows 17 …… Latch bellows 18 …… Inner extension tube 19 …… Outer extension tube 20 …… Acceleration spring 21 …… Acceleration tube 22 …… Gripper opening / closing rod 23 …… Connection link 24 …… Control rod 25… ... Lower guide tube 26 ... Gripper 27 ... Drop buffer 28 ... Gripper opening and closing drive unit 30 ... Fuel 31 ... Fuel entry and exit unit delivery position

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】制御棒上方の炉心上部機構内に設置され、
制御棒の掴みおよび放し、引抜き、スクラム機能と、燃
料の掴みおよび放し、挿入、引抜き機能とを備えた制御
棒駆動機構内蔵燃料交換機において、この制御棒駆動機
構内蔵燃料交換機は、炉心の内側領域のみを取扱う内側
燃料交換装置と、炉心の外側領域のみを取扱う外側燃料
交換装置とから成ることを特徴とする制御棒駆動機構内
蔵燃料交換機。
1. A core upper mechanism installed above a control rod,
In a fuel exchange machine with a control rod drive mechanism having control rod gripping and releasing, withdrawing and scrum functions, and fuel grasping and releasing, insertion and withdrawal functions, the control rod driving mechanism incorporated fuel exchange device is provided in the inner region of the core. A refueling machine with a control rod drive mechanism, comprising an inner refueling device that handles only the outer refueling device that handles only the outer region of the core.
JP61068650A 1986-03-28 1986-03-28 Refueling machine with built-in control rod drive mechanism Expired - Lifetime JPH0634080B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61068650A JPH0634080B2 (en) 1986-03-28 1986-03-28 Refueling machine with built-in control rod drive mechanism

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61068650A JPH0634080B2 (en) 1986-03-28 1986-03-28 Refueling machine with built-in control rod drive mechanism

Publications (2)

Publication Number Publication Date
JPS62226097A JPS62226097A (en) 1987-10-05
JPH0634080B2 true JPH0634080B2 (en) 1994-05-02

Family

ID=13379787

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61068650A Expired - Lifetime JPH0634080B2 (en) 1986-03-28 1986-03-28 Refueling machine with built-in control rod drive mechanism

Country Status (1)

Country Link
JP (1) JPH0634080B2 (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP7733859B1 (en) * 2024-07-12 2025-09-03 三菱Fbrシステムズ株式会社 Method for installing reactor structure of fast reactor
WO2026014007A1 (en) * 2024-07-12 2026-01-15 三菱Fbrシステムズ株式会社 Installation method for reactor structure of fast reactor

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6039591A (en) * 1983-08-12 1985-03-01 株式会社東芝 Nuclear reactor

Also Published As

Publication number Publication date
JPS62226097A (en) 1987-10-05

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