JPH01116497A - Boiling water type nuclear reactor - Google Patents

Boiling water type nuclear reactor

Info

Publication number
JPH01116497A
JPH01116497A JP62272976A JP27297687A JPH01116497A JP H01116497 A JPH01116497 A JP H01116497A JP 62272976 A JP62272976 A JP 62272976A JP 27297687 A JP27297687 A JP 27297687A JP H01116497 A JPH01116497 A JP H01116497A
Authority
JP
Japan
Prior art keywords
steam
pressure vessel
reactor
control rod
reactor core
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
JP62272976A
Other languages
Japanese (ja)
Inventor
Koichi Matsumoto
宏一 松本
Shozo Nakamura
中村 昭三
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 JP62272976A priority Critical patent/JPH01116497A/en
Publication of JPH01116497A publication Critical patent/JPH01116497A/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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、原子炉の構造に係り、特に、安全性。[Detailed description of the invention] [Industrial application field] The present invention relates to the structure of nuclear reactors, and in particular to safety.

経済性の向上した沸騰水型原子炉に関する。Concerning boiling water reactors with improved economic efficiency.

(従来の技術〕 従来の沸騰水型原子炉は、コロナ社[原子カプラント工
学」p75に記載のように、炉心上部にシュラウドヘッ
ド、気水分離器、蒸気乾燥器等が設置されているため、
制御棒を下から挿入せねばならず、制御棒駆動機構が複
雑になる上に、事故時の駆動の信頼性に開運があった。
(Conventional technology) Conventional boiling water reactors have a shroud head, steam separator, steam dryer, etc. installed in the upper part of the reactor core, as described in Corona Publishing [Atomic Coplant Engineering] p. 75.
The control rods had to be inserted from below, which made the control rod drive mechanism complicated, and the reliability of the drive in the event of an accident was compromised.

−また、圧力容器の胴長が加工木型炉に比して長くなっ
ており、建設コストが嵩んでいた。さらに、燃料交換の
際には、圧力容器のふたを取りはずした後、炉心上部の
、気水分離器、蒸気乾燥器を取はずしてから燃料交換を
行なっていた。
-Also, the length of the pressure vessel was longer than that of the wooden processing furnace, which increased construction costs. Furthermore, during fuel exchange, the lid of the pressure vessel was removed, and the steam separator and steam dryer at the top of the core were removed before fuel exchange.

(発明が解決しようとする問題点〕 上記従来技術は、重力に反して制御棒を挿入するため、
制御棒駆動機構が複雑になり、また、事故時に、制御棒
が駆動するかどうかについても。
(Problems to be solved by the invention) In the above-mentioned conventional technology, since the control rod is inserted against gravity,
The control rod drive mechanism is becoming more complex, and it also concerns whether the control rods will be driven in the event of an accident.

重力を利用して上部から自然に落下させる場合と比較し
て、信頼性が劣っていた。
It was less reliable than letting it fall naturally from above using gravity.

さらに、圧力容器は、気水分離器、蒸気乾燥器等をもつ
ため胴長が長く、また、燃料交換時には気水分離器、蒸
気乾燥器を撤去した後に、燃料の交換を行なうなど、建
設、運転コストを引き上げる要因となっていた。
Furthermore, pressure vessels have a long body because they have a steam separator, steam dryer, etc., and when replacing fuel, the steam separator and steam dryer must be removed before the fuel is replaced. This was a factor that raised operating costs.

本発明の目的は、制御棒を上部から挿入することによる
安全性の向上や、圧力容器胴長の短縮、燃料交換時の工
数低減による経済性の向上を図ることにある。
An object of the present invention is to improve safety by inserting control rods from the top, shorten the length of the pressure vessel, and improve economic efficiency by reducing the number of man-hours required for fuel exchange.

〔問題点を解決するための手段〕[Means for solving problems]

上記目的は、気水分離器、蒸気乾燥器の小型化を図り、
圧力容器の外部に設置することにより。
The above purpose is to reduce the size of steam separators and steam dryers,
By installing it outside the pressure vessel.

達成される。achieved.

〔作用〕[Effect]

気水分離器、蒸気乾燥器の小型化を図り、圧力容器の外
部に設置したため、炉心の上部に障害物がなく、制御棒
の上部からの挿入が可能となる。
The steam separator and steam dryer have been miniaturized and installed outside the pressure vessel, so there are no obstacles in the upper part of the reactor core, and control rods can be inserted from the top.

また、燃料交換時に、圧力容器の蓋を開けるのみで交換
が可能となり、工数の低減が図れる。さらに、炉心上部
の空間をせばめられ、圧力容器の胴長を短かくすること
ができる。
Furthermore, when replacing fuel, it is possible to replace the fuel simply by opening the lid of the pressure vessel, reducing the number of man-hours. Furthermore, the space above the core can be narrowed, and the length of the pressure vessel can be shortened.

〔実施例〕〔Example〕

以下、本発明の一実施例を第1図により説明する。第1
図は本発明装置の系統図であり、第2図から第4図は他
の実施例の系統図である。
An embodiment of the present invention will be described below with reference to FIG. 1st
The figure is a system diagram of the apparatus of the present invention, and FIGS. 2 to 4 are system diagrams of other embodiments.

まず、第1図を用いて各機器の構成を説明する。First, the configuration of each device will be explained using FIG.

図において、原子炉圧力容器1内は基本的には原子炉炉
心2.制御棒4が挿入される制御棒案内管3、ジェット
ポンプ15により構成される。制御棒4は制御棒駆動装
置5によって駆動される。原子炉圧力容器1の上部より
主蒸気管6が伸長し、気水分離圧力容器7を介し、発電
用タービン12に達する。気水分離圧力容器7の中には
、気水分離器8と蒸気乾燥器9.シュラ°ウドヘッド1
0が収納されており、気水分離圧力容器下部と戻り配管
14をドレン配管12が結んでいる。発電用タービン1
2の下部には、復水器13が設置され、戻り配管14は
、原子炉圧力容器1に接続する。
In the figure, the interior of the reactor pressure vessel 1 basically consists of a reactor core 2. It is composed of a control rod guide tube 3 into which a control rod 4 is inserted, and a jet pump 15. The control rods 4 are driven by a control rod drive device 5. A main steam pipe 6 extends from the upper part of the reactor pressure vessel 1 and reaches a power generation turbine 12 via a steam/water separation pressure vessel 7. Inside the steam/water separation pressure vessel 7, there are a steam separator 8 and a steam dryer 9. Shura ° Wood Head 1
A drain pipe 12 connects the lower part of the steam/water separation pressure vessel and the return pipe 14. Power generation turbine 1
A condenser 13 is installed at the bottom of the reactor pressure vessel 1 , and a return pipe 14 is connected to the reactor pressure vessel 1 .

次に、各機器の作用を説明する。Next, the function of each device will be explained.

原子炉炉心2で炉水は蒸気となり、主蒸気管6に直接進
入した後、気水分離圧力容器7に進入する。気水分離圧
力容器7内には、シュラウドヘッド10の上に小型で高
性能な気水分離器8及び蒸気乾燥器9があり、蒸気はこ
れらを通るうちに湿分が除去され、乾いた蒸気となる。
Reactor water turns into steam in the reactor core 2, directly enters the main steam pipe 6, and then enters the steam-water separation pressure vessel 7. Inside the steam/water separation pressure vessel 7, there is a small, high-performance steam/water separator 8 and a steam dryer 9 on the shroud head 10, and as the steam passes through these, moisture is removed and the steam becomes dry steam. becomes.

気水分離圧力容器7の中で除去された、水分は、シュラ
ウドヘッド10の上部を伝わり、ドレン配管11を通っ
て戻り配管14に混入し、炉心に戻る。気水分離器8.
蒸気乾燥器9を通った蒸気はタービン12に導かれた後
、復水器11で水になり戻り配管14を通り、ジェット
ポンプ15で炉心に戻る。
The moisture removed in the steam/water separation pressure vessel 7 travels through the upper part of the shroud head 10, passes through the drain pipe 11, enters the return pipe 14, and returns to the reactor core. Steam water separator8.
The steam that has passed through the steam dryer 9 is led to the turbine 12, then turns into water in the condenser 11, passes through the return pipe 14, and returns to the core by the jet pump 15.

本発明の系統において、気水分離器8、蒸気乾燥器9は
、原子炉圧力容器1の外部に設置したため、1)シュラ
ウドヘッド10が炉心全体を覆う必要がない。2)炉心
と離れているため、任意の形状をとりやすい。等の観点
から、湿分除去に最適な形状に設計することができ、小
型化及び高性能化できる。従来の形状のままで気水分離
器8.蒸気乾燥器9を原子炉圧力容器1の外に出すと、
気水分離圧力容器7が大きくなってしまう。気水分離器
8.蒸気乾燥器9を小型化し、気水分離圧力容器7を小
型化できれば設備も簡素となる。
In the system of the present invention, the steam separator 8 and the steam dryer 9 are installed outside the reactor pressure vessel 1, so 1) there is no need for the shroud head 10 to cover the entire reactor core. 2) Since it is separated from the reactor core, it can easily take any shape. From these points of view, it is possible to design the shape to be optimal for moisture removal, and it is possible to downsize and improve performance. 8. Steam/water separator with the conventional shape. When the steam dryer 9 is taken out of the reactor pressure vessel 1,
The steam/water separation pressure vessel 7 becomes large. Steam water separator8. If the steam dryer 9 can be made smaller and the steam/water separation pressure vessel 7 can be made smaller, the equipment will also be simpler.

第1図の系統では、次の効果が期待できる。第一に、気
水分離器8.蒸気乾燥器9の小型化に伴い1M子炉圧力
容器1と気水分離圧力容器7を合わせた設備の胴長が短
かくでき、原子炉格納容器の高さを低くすることができ
る。第二に、気水分離器8.蒸気乾燥器9で、万一、故
障が発生しても、炉心2と離れているため、影響が炉心
2まで及ばない。第三に、炉心2の上部の構造物がなく
なったことにより、制御棒システムを上部に設置するこ
とができ、制御棒駆動装置5の簡素化や。
The system shown in Figure 1 can be expected to have the following effects. First, the steam/water separator 8. With the miniaturization of the steam dryer 9, the length of the equipment including the 1M slave reactor pressure vessel 1 and the steam/water separation pressure vessel 7 can be shortened, and the height of the reactor containment vessel can be reduced. Second, the steam/water separator 8. Even if a failure occurs in the steam dryer 9, it will not affect the reactor core 2 because it is separated from the reactor core 2. Thirdly, since there is no structure above the reactor core 2, the control rod system can be installed at the top, which simplifies the control rod drive device 5.

事故時の制御棒4の自重落下ができることによる、信頼
性が一層向上する。第四に、原子炉圧力容器1の上部蓋
を開けるのみで、燃料棒の交換が可能となり、従来気水
分離器や蒸気乾燥器を除去していた工程が省け、燃料交
換時間が短縮できる。
Reliability is further improved by allowing the control rod 4 to fall under its own weight in the event of an accident. Fourthly, fuel rods can be replaced simply by opening the upper cover of the reactor pressure vessel 1, eliminating the conventional process of removing a steam separator and a steam dryer, and shortening the fuel replacement time.

第2図には、気水分離器圧力容器7の他の実施例を示す
。気水分離器8と蒸気乾燥器9を主蒸気管6の中に設置
できる形状とすれば、気水分離用外管16を設け、二重
管構造にするのみで、ドレンの回収もできる。
FIG. 2 shows another embodiment of the steam/water separator pressure vessel 7. If the steam separator 8 and the steam dryer 9 are shaped so that they can be installed in the main steam pipe 6, drain can be recovered simply by providing the outer pipe 16 for steam and water separation and creating a double pipe structure.

第3図は、第2図の気水分離用外管16の別の実施例で
ある。気水分離器8、蒸気乾燥器9を横置きタイプにす
れば、従来の沸騰水型原子炉の主蒸気管6と同様に、圧
力容器から真横に主蒸気管6を延長でき、その結果、主
蒸気管6を、長くすることなく、また、第2図と比較し
主蒸気管6が水平方向にあるため原子炉格納容器の高さ
を低くすることができる。
FIG. 3 shows another embodiment of the outer tube 16 for steam/water separation shown in FIG. 2. If the steam separator 8 and the steam dryer 9 are of the horizontal type, the main steam pipe 6 can be extended right sideways from the pressure vessel, similar to the main steam pipe 6 of a conventional boiling water reactor, and as a result, The height of the reactor containment vessel can be lowered without making the main steam pipe 6 longer, and because the main steam pipe 6 is in a horizontal direction compared to FIG. 2.

第4図は、第3図と同様の実施例であるが、制御棒シス
テムが原子炉圧力容器1の下部についており、現行の沸
騰水形原子炉と同様である。燃料交換時の圧力容器蓋の
取りはずしのみを考えれば第4図の構造の方が、作業を
簡素化できる。
FIG. 4 shows an embodiment similar to FIG. 3, but the control rod system is attached to the bottom of the reactor pressure vessel 1, similar to current boiling water reactors. Considering only the removal of the pressure vessel lid during fuel exchange, the structure shown in FIG. 4 can simplify the work.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、炉心全体を覆う大きさのシュラウドヘ
ッドが必要でなくなり、装置の小形化が可能となり、原
子炉格納容器の高きを低くでき、制御棒システムを炉心
上部に設置でき、事故時に制御棒が自重で落下するため
安全性が向上する。
According to the present invention, there is no need for a shroud head large enough to cover the entire reactor core, the equipment can be made more compact, the height of the reactor containment vessel can be lowered, the control rod system can be installed at the top of the core, and in the event of an accident Safety is improved because the control rod falls under its own weight.

また、原子炉圧力容器の蓋を開けるのみで、燃料交換が
できるため、燃料交換の工数が削減される。
Additionally, since fuel can be replaced simply by opening the reactor pressure vessel lid, the number of man-hours required for fuel replacement is reduced.

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

第1図は本発明の一実施例の系統図、第2図。 第3図、第4図は本発明の他の実施例の系統図である。 FIG. 1 is a system diagram of an embodiment of the present invention, and FIG. 2 is a system diagram of an embodiment of the present invention. FIGS. 3 and 4 are system diagrams of other embodiments of the present invention.

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器と、原子炉炉心と、前記原子炉炉心
の反応を制御する制御棒と、前記制御棒を前記原子炉炉
心に導くための制御棒案内管と、前記制御棒を駆動する
制御棒駆動装置と、前記原子炉炉心で発生した蒸気の水
分除去装置と、蒸気をタービンに導く主蒸気管とより成
る原子炉において、 前記水分除去装置を、前記主蒸気管の途中に設けた縦向
き、もしくは、横向きの水分除去用の圧力容器内に設置
したことを特徴とする沸騰水型原子炉。
[Scope of Claims] 1. A reactor pressure vessel, a reactor core, a control rod for controlling a reaction in the reactor core, and a control rod guide tube for guiding the control rod to the reactor core; In a nuclear reactor comprising a control rod drive device that drives the control rods, a moisture removal device for steam generated in the reactor core, and a main steam pipe that guides the steam to a turbine, the moisture removal device is connected to the main steam A boiling water nuclear reactor characterized by being installed in a vertical or horizontal pressure vessel for water removal installed in the middle of a pipe.
JP62272976A 1987-10-30 1987-10-30 Boiling water type nuclear reactor Pending JPH01116497A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62272976A JPH01116497A (en) 1987-10-30 1987-10-30 Boiling water type nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62272976A JPH01116497A (en) 1987-10-30 1987-10-30 Boiling water type nuclear reactor

Publications (1)

Publication Number Publication Date
JPH01116497A true JPH01116497A (en) 1989-05-09

Family

ID=17521412

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62272976A Pending JPH01116497A (en) 1987-10-30 1987-10-30 Boiling water type nuclear reactor

Country Status (1)

Country Link
JP (1) JPH01116497A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5319689A (en) * 1992-03-12 1994-06-07 General Electric Company Compactable phase-separator assembly for dual-phase nuclear reactor
FR3002274A1 (en) * 2013-02-15 2014-08-22 Commissariat Energie Atomique ELECTRICITY PRODUCTION PLANT COMPRISING A DEVICE FOR PRODUCING WATER VAPOR OF REDUCED HEIGHT, APPLICATION TO REP AND REB REACTORS

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5319689A (en) * 1992-03-12 1994-06-07 General Electric Company Compactable phase-separator assembly for dual-phase nuclear reactor
FR3002274A1 (en) * 2013-02-15 2014-08-22 Commissariat Energie Atomique ELECTRICITY PRODUCTION PLANT COMPRISING A DEVICE FOR PRODUCING WATER VAPOR OF REDUCED HEIGHT, APPLICATION TO REP AND REB REACTORS
WO2014125442A3 (en) * 2013-02-15 2015-04-23 Commissariat A L'energie Atomique Et Aux Energies Alternatives Electricity generation facility comprising a device for producing steam of reduced height, application to pwr and bwr reactors
US10510453B2 (en) 2013-02-15 2019-12-17 Commissariat A L'energie Atomique Et Aux Energies Alternatives Electricity generation facility comprising a device for producing steam of reduced height, application to PWR and BWR reactors

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