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JPS60107596A - Boiling-water type reactor - Google Patents

Boiling-water type reactor

Info

Publication number
JPS60107596A
JPS60107596A JP58214110A JP21411083A JPS60107596A JP S60107596 A JPS60107596 A JP S60107596A JP 58214110 A JP58214110 A JP 58214110A JP 21411083 A JP21411083 A JP 21411083A JP S60107596 A JPS60107596 A JP S60107596A
Authority
JP
Japan
Prior art keywords
reactor
pump
water
pressure vessel
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
JP58214110A
Other languages
Japanese (ja)
Inventor
青木 忠
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP58214110A priority Critical patent/JPS60107596A/en
Publication of JPS60107596A publication Critical patent/JPS60107596A/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

  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (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】 〔発明の技術分野〕 この発明は原子炉圧力容器に畢付けられた原子炉内循環
ポンプを備えた沸騰水型原子炉に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] This invention relates to a boiling water nuclear reactor equipped with an intra-reactor circulation pump attached to a reactor pressure vessel.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

従来の沸騰水型原子炉は、第1図に示すように原子炉圧
力容器1内にジェットポンプ2を数台乃至十数台備え、
このジェットポンプ2を再循環ポンダ3からの駆動水で
作動させ、炉水を循環させるものが使用されている。
A conventional boiling water reactor is equipped with several to ten or more jet pumps 2 in a reactor pressure vessel 1, as shown in FIG.
This jet pump 2 is operated by driving water from a recirculation ponder 3 to circulate reactor water.

しかし、ジェットポンプ2を備えた沸騰水型原子炉は、
再循環ポンプ3が原子炉圧力容器1の外部に設置される
ため、配管等の構造が複雑となる不具合があった。
However, a boiling water reactor equipped with jet pump 2
Since the recirculation pump 3 was installed outside the reactor pressure vessel 1, there was a problem in that the structure of the piping etc. was complicated.

このため、原子炉圧力容器に循環ポンプとしての原子炉
内循環ポンプを直接取付けた沸騰水型原子炉が開発され
るようになった。この沸騰水型原子炉は第2図および第
3図に示すように原子炉圧力容器10内に炉心11を支
持する円筒状の炉心シュラウド12を収容し、このシュ
ラウP12と原子炉圧力容器10内周壁との間に形成さ
れる環状の通路13に複数台の原子炉内循環ポンプ14
のポンプ部14aが据付けられる。原子炉内循環ポンプ
14のモータ部(図示せず)は原子炉圧力容器10の底
部から下方に突出するようにして設けられる。
For this reason, boiling water reactors have been developed in which an in-reactor circulation pump as a circulation pump is directly attached to the reactor pressure vessel. As shown in FIGS. 2 and 3, this boiling water reactor houses a cylindrical core shroud 12 that supports a reactor core 11 in a reactor pressure vessel 10. A plurality of in-reactor circulation pumps 14 are installed in an annular passage 13 formed between the peripheral wall and the annular passage 13.
A pump section 14a is installed. A motor section (not shown) of the reactor circulation pump 14 is provided so as to protrude downward from the bottom of the reactor pressure vessel 10.

ところで、原子炉圧力容器10内の炉水は原子炉内循環
ポンプ14の作動によシ、環状の通路13から炉水流通
口16を経て炉心下部17に送られる。この炉水は炉心
下部から反転上昇し炉心11内を通る。
By the way, reactor water in the reactor pressure vessel 10 is sent to the lower core 17 from the annular passage 13 through the reactor water flow port 16 by the operation of the reactor circulation pump 14 . This reactor water reversely rises from the lower part of the reactor core and passes through the inside of the reactor core 11.

炉水が炉心1工を通る間に加熱されて気液二相流となり
、この気液二相流は図示しない気水分離器で水と蒸気と
に分離される。分離された蒸気は蒸気乾燥器を経て乾き
蒸気となった後、蒸気タービンに送られ、この蒸気ター
ビンを駆動するようになっている。また、分離させられ
た炉水は環状通路13に案内され、原子炉内循環ポンプ
14のポンプ作動により炉心下部に循環せしめられるよ
うになっている。
While the reactor water passes through the reactor core, it is heated and becomes a gas-liquid two-phase flow, and this gas-liquid two-phase flow is separated into water and steam by a steam separator (not shown). After the separated steam passes through a steam dryer and becomes dry steam, it is sent to a steam turbine to drive the steam turbine. Further, the separated reactor water is guided to an annular passage 13 and circulated to the lower part of the reactor core by the operation of an intra-reactor circulation pump 14.

ところで、環状通路13は炉心下部17から仕切壁とし
ての隔壁18によシ隔てられておシ、この隔壁に原子炉
内循環ポンプ14のポンプ部14aが貫通するように設
けられる。このポンプ部14aの直径はジェットポンプ
2の直径よシ大きく、このため、原子炉−内循環ポンプ
14を収容した環状通路13の通路幅は、ジェットポン
プ2を設置した通路幅より大きく、環状通路の断面積も
太きい。
Incidentally, the annular passage 13 is separated from the core lower part 17 by a partition wall 18 serving as a partition wall, and a pump portion 14a of the in-reactor circulation pump 14 is provided so as to penetrate this partition wall. The diameter of this pump part 14a is larger than the diameter of the jet pump 2, and therefore the passage width of the annular passage 13 that accommodates the intra-reactor circulation pump 14 is larger than the passage width in which the jet pump 2 is installed. The cross-sectional area of is also large.

一方、原子炉内循環ポンプ14の設置台数は、ジェット
ポンプ2の設置台数より少なく、原子炉内循環ポンプ1
4の設置間隔は広い。したがって、1台の原子炉内循環
ポンプ14が取扱う炉水流量が大きく、環状通路【3内
を流れる炉水は原子炉内循環ポンプ14のポンプ部14
aに吸い込まれる際、急激に縮流され、流速が大きくな
る。
On the other hand, the number of in-reactor circulation pumps 14 installed is smaller than the number of jet pumps 2 installed, and the number of in-reactor circulation pumps 14 is smaller than the number of jet pumps 2 installed.
4 has a wide installation interval. Therefore, the flow rate of reactor water handled by one in-reactor circulation pump 14 is large, and the reactor water flowing through the annular passage [3] is
When being sucked into a, the flow is rapidly contracted and the flow velocity increases.

また、特定の原子炉内循環ポンプ14が故障した場合、
その部分の炉水が隔壁18に沿って隣接する原子炉内循
環ポンプ14へ逆流し、渦流の発生が予想される。この
渦流の発生によりこの部分を流れる炉水が乱流となり、
原子炉内循環ポンプのポンプ効率が低下したり、発生し
た旋回流によシキャビテーションが生じ、ポンプ機器に
損傷を与える恐れがあった。
In addition, if a specific reactor circulation pump 14 breaks down,
It is expected that the reactor water in that area will flow back along the bulkhead 18 to the adjacent reactor circulation pump 14, creating a vortex. Due to the generation of this vortex, the reactor water flowing through this area becomes turbulent, and
There was a risk that the efficiency of the circulation pump in the reactor would decrease and cavitation would occur due to the generated swirling flow, causing damage to pump equipment.

〔発明の目的〕[Purpose of the invention]

この発明は上述した点を考慮し、旋回流によるキャビテ
ーションの発生を有効的に防止し、ポンプ効率の低下や
ポンプ機器の損傷を未然にかつ確実に防ぐようにした沸
騰水型原子炉を提供することを目的とする。
The present invention takes the above points into consideration and provides a boiling water nuclear reactor that effectively prevents the occurrence of cavitation due to swirling flow and prevents a decrease in pump efficiency and damage to pump equipment. The purpose is to

〔発明の概要〕[Summary of the invention]

上述した目的を達成するために、この発明に係る沸騰水
型原子炉は、原子炉圧力容器内に炉心シュラウドを収容
し、この炉心シュラウドと原子炉圧力容器との間に環状
の通路を形成し、この環状通路の下部に設けられた隔壁
に複数の原子炉内循環ポンプのポンプ部を取付けたもの
において、上記原子炉内循環ポンプの各ポンプ部間の環
状空間に、仁の環状空間の下部を分割する仕切板を放射
状に設けたものである。
In order to achieve the above-mentioned object, a boiling water nuclear reactor according to the present invention accommodates a core shroud in a reactor pressure vessel, and forms an annular passage between the core shroud and the reactor pressure vessel. , in which the pump parts of a plurality of reactor circulation pumps are attached to the partition wall provided at the lower part of this annular passage, the lower part of the inner annular space is installed in the annular space between each pump part of the above-mentioned reactor circulation pump. Partition plates are installed radially to divide the area.

〔発明の実施例〕[Embodiments of the invention]

以下、この発明に係る沸騰水型原子炉の好ましい実施例
について添付図面を参照して説明する。
Hereinafter, preferred embodiments of the boiling water reactor according to the present invention will be described with reference to the accompanying drawings.

第4図において、符号加は沸騰水型原子炉の原子炉圧力
容器を示し、この原子炉圧力容器内に円筒状の炉心シュ
ラウド21が同心円状に収容される。炉心シュラウP2
1は原子炉圧力容器銀の底部に立設される一方、シュラ
ウ)421内には多数の燃料集合体を装架した炉心内が
構成される。炉心nの上方には気水分離器乙が設置され
、との気水分離器nで炉心nから流出された気液二相流
を蒸気と水とに分離させている。このうち、蒸気は気水
分離器乙の上方に設置された蒸気乾燥器冴を通って主蒸
気ノズル6に案内され、図示しない主蒸気管を経て蒸気
タービン(図示せず)に送られるようになっている。
In FIG. 4, the reference numeral "addition" indicates a reactor pressure vessel of a boiling water reactor, and a cylindrical core shroud 21 is housed concentrically within this reactor pressure vessel. Core shrou P2
1 is installed upright at the bottom of the reactor pressure vessel, while the inside of the reactor core, in which a large number of fuel assemblies are mounted, is constructed within the shroud 421. A steam-water separator B is installed above the core n, and the steam-water separator B separates the gas-liquid two-phase flow flowing out from the core n into steam and water. Among these, the steam is guided to the main steam nozzle 6 through a steam dryer installed above the steam separator B, and is sent to a steam turbine (not shown) via a main steam pipe (not shown). It has become.

一方、炉心内の下方には、炉心内に制御棒を出し入れす
る制御棒駆動機構nが設けられている。
On the other hand, a control rod drive mechanism n for moving control rods in and out of the reactor core is provided below within the reactor core.

この制御棒駆動機構27の作動によシ制御棒赤炉心乙に
出し入れされ、原子炉の運転が制御される。
The operation of the control rod drive mechanism 27 causes the control rods to be moved in and out of the red reactor core B, thereby controlling the operation of the nuclear reactor.

また、原子炉圧力容器かと炉心シュラウド21との間に
はダウンカマと称される環状の通路四が形成され、この
環状通路あの下部は仕切壁としての環状の隔壁29によ
シ仕切られている。隔壁四は炉心シュラウド21下部と
原子炉炉心部の底部近傍の内周壁とを一体的に連結した
ものである。上記環状通路路を仕切る隔壁四に原子炉内
循環ポンプ加のポンプ部31が設けられる。原子炉内循
環ポンプ加は原子炉圧力容器かの内周壁に沿って複数台
設置される。
Further, an annular passage 4 called a downcomer is formed between the reactor pressure vessel and the core shroud 21, and the lower part of this annular passage is partitioned off by an annular partition wall 29 serving as a partition wall. The partition wall 4 integrally connects the lower part of the core shroud 21 and the inner circumferential wall near the bottom of the reactor core. A pump section 31 for supplying a circulation pump within the nuclear reactor is provided on the partition wall 4 that partitions the annular passageway. Multiple reactor circulation pumps are installed along the inner peripheral wall of the reactor pressure vessel.

原子炉内循環ポンプ加は原子炉圧力容器肋内に位置され
るポンプ部31とこのポンプ部を駆動させるモータ部3
2とを有し、モータ部32は原子炉圧力容器加昇に突出
して設置されるモータ部32からの回転駆動力はポンプ
シャツ)33を介してポンプ部31に伝達される。ポン
プ部31は第5図および第6図に示すようにポンプシャ
フト邪に軸装されるインペラおとこのインペラあを覆う
円筒状のディフューザあとを有し、ディフューザ36は
隔壁四を貫通するようにして装着される。
The reactor circulation pump includes a pump section 31 located within the reactor pressure vessel and a motor section 3 that drives this pump section.
The motor section 32 is installed protruding from the reactor pressure vessel.The rotational driving force from the motor section 32 is transmitted to the pump section 31 via a pump shirt 33. As shown in FIGS. 5 and 6, the pump section 31 has a cylindrical diffuser mark that covers the impeller and the impeller mounted on the pump shaft, and the diffuser 36 extends through the partition wall 4. It will be installed.

上記原子炉内循環ポンプ(9)のポンプ部31の真下に
対応した炉心シュラウド21の下端周壁部には、炉水流
通口開がそれぞれ形成されている。炉水流通口あの間の
部分は厚肉に形成されて脚部39を構成しておシ、これ
らの脚部39によって炉心シュラウド21は支持され、
炉心部の荷重を支えている。
Reactor water flow openings are formed in the lower end circumferential wall portion of the core shroud 21, which corresponds to the position immediately below the pump portion 31 of the reactor circulation pump (9). The portion between the reactor water flow openings is formed thickly and constitutes leg portions 39, and the core shroud 21 is supported by these leg portions 39.
It supports the load of the reactor core.

しかして、原子炉内循環ポンプ30のポンプ部31から
下方に吐出された炉水は、炉水流通白羽を経て炉心下部
40に案内される。
Thus, the reactor water discharged downward from the pump section 31 of the intra-reactor circulation pump 30 is guided to the lower core 40 through the reactor water distribution line.

また、原子炉内循環ポンプ加のポンプ部31は原子炉圧
力容器加の内周壁に沿い、周方向に適宜間隔をおいて設
置される。上記各ポンプ部31 、31間には環状通路
列を周方向に数分割乃至十数分割する矩形の仕切板42
が介装される。仕切板42は環状通路あの下部に放射状
に配設され、その下部は環状の隔壁円上に固定される。
Further, the pump parts 31 of the reactor circulation pump are installed along the inner circumferential wall of the reactor pressure vessel at appropriate intervals in the circumferential direction. A rectangular partition plate 42 is provided between each of the pump parts 31 and 31 to divide the annular passage row into several to ten-odd parts in the circumferential direction.
is interposed. The partition plate 42 is arranged radially at the lower part of the annular passage, and the lower part thereof is fixed on the annular partition circle.

仕切板42の一側端は炉心シュラウド21の外周壁に、
その反対側の側端は原子炉圧力容器加の内周壁にそれぞ
れ固定される。
One end of the partition plate 42 is connected to the outer peripheral wall of the core shroud 21,
The opposite side ends are respectively fixed to the inner circumferential wall of the reactor pressure vessel.

なお、第4図において、符号44は環状の給水スパージ
ャであシ、この給水スパージャ44には図示しない復水
器内の給水が給水管45を経て供給されるようになって
おシ、給水スノぐ一ジャ劇に案内された給水はここから
原子炉圧力容器銀白に噴出される。
In addition, in FIG. 4, reference numeral 44 is an annular water supply sparger, and water in a condenser (not shown) is supplied to this water supply sparger 44 through a water supply pipe 45. The water supplied to the reactor is spouted into the reactor pressure vessel Ginpaku from here.

次に、この発明に係る沸騰水m原子炉の作用について説
明する。
Next, the operation of the boiling water m nuclear reactor according to the present invention will be explained.

原子炉圧力容器に内の炉水は給水スパージャ44から供
給された給水と混合されて環状通路路に案内され、この
環状通路おから原子炉内循環ポンプ加のポンプ作用を受
けて炉心下部40に送られる。
The reactor water in the reactor pressure vessel is mixed with the feed water supplied from the feed water sparger 44 and guided to the annular passageway, where the okara is pumped by the reactor circulation pump and flows into the lower core 40. Sent.

炉心下部40に案内された炉水けここで反転して原子炉
炉心部に送られ、この炉心部を通る間に加熱作用を受け
て沸騰し、気液二相流となる。気液二相流は炉心n上部
の気水分離器nで蒸気と水とに分離される。
The reactor water guided to the lower part of the reactor core 40 is turned around and sent to the reactor core, and while passing through the reactor core, it is heated and boiled, becoming a gas-liquid two-phase flow. The gas-liquid two-phase flow is separated into steam and water by a steam-water separator n above the core n.

気水分離器nにて分離された蒸気は蒸気乾燥器別で乾燥
されて乾き蒸気となシ、この蒸気は主蒸気ノズル5から
図示しない主蒸気管を経て蒸気タービンに送られ、蒸気
タービンを駆動させる。蒸気タービンを駆動することに
より膨張した蒸気は、復水器(図示せず)に送られて凝
縮作用を受けて復水となる。この復水は途中で熱処理さ
れて加熱されて給水管45から給水スパージャ44に送
られ、この給水ス/e−ジャ44から原子炉圧力容器銀
白に供給される。
The steam separated in the steam separator n is dried in a separate steam dryer to become dry steam, and this steam is sent from the main steam nozzle 5 to the steam turbine via the main steam pipe (not shown), and the steam turbine is drive. Steam expanded by driving the steam turbine is sent to a condenser (not shown) where it is condensed and becomes condensed water. This condensate is heat-treated on the way and is sent from the water supply pipe 45 to the water supply sparger 44, and from this water supply sparger 44 is supplied to the reactor pressure vessel Ginpaku.

一方、気水分離器るで分離させられた水は、再びダウン
カマとしての環状通路路に案内され、原子炉内循環ポン
プ(9)のポンプ作用によシ、環状通路あから炉心下部
40に案内される。このようにして1原子炉圧力容器肋
内の炉水は原子炉内循環ポンプ部のポンプ作用により内
部循環せしめられる。
On the other hand, the water separated by the steam-water separator is guided again to the annular passageway as a downcomer, and guided from the annular passageway to the lower core 40 by the pumping action of the reactor circulation pump (9). be done. In this way, the reactor water within the ribs of one reactor pressure vessel is internally circulated by the pumping action of the reactor circulation pump section.

このように、原子炉圧力容器銀白の炉水は環状通路あ内
を流下し、原子炉内循環ポンプ加のポンプ作用によシ下
方に吐出され、炉水流通口開から炉心下部40に案内さ
れる。この原子炉内循環ポンプ加の枢動中に、特定の原
子炉内循環ポンプ加の作動が何らかの原因で停止すると
、その節分の炉水に逆流が生ずることがあるが、この炉
水は、仕切板420面に沿って隣接のポンプ部31にス
ムーズに乱れることなく案内されるので、流れがスムー
ズになり渦流の発生が効果的に防止される。したがって
、キャビテーション等の発生を有効に防止でき、原子炉
内循環−ンゾ加のポンプ効率の低下を防ぐことができる
In this way, the reactor water in the reactor pressure vessel Ginpaku flows down the annular passage, is discharged downward by the pumping action of the reactor circulation pump, and is guided to the lower core 40 through the reactor water flow opening. Ru. If the operation of a particular reactor circulation pump stops for some reason during this pivoting of the reactor circulation pump, a backflow may occur in the reactor water for that section, but this reactor water is Since it is guided smoothly and without disturbance to the adjacent pump section 31 along the surface of the plate 420, the flow becomes smooth and the generation of vortices is effectively prevented. Therefore, the occurrence of cavitation and the like can be effectively prevented, and a decrease in the efficiency of the pump for circulation inside the reactor can be prevented.

〔発明の効果〕〔Effect of the invention〕

以上に述べたようにこの発明に係る沸騰水型原子炉にお
いては、原子炉内循環ポンプの各ポンプ部間の環状空間
に、この環状空間の下部を分割する仕切板を放射状に設
けたから、環状空間の下部は周方向に沿って複数に分割
され、分割された空間内に原子炉内循環ポンプのポンプ
部が収容される。したがって、特定の原子炉内循環ポン
プが何らかの原因で停止しても、環状通路内を流下する
炉水は仕切板に案内され、かつ停止ポンプ部の炉水は、
仕切板に沿い、この仕切板を乗9越えて隣接するポンプ
部にスムーズに吸込まれるので、渦流の発生を効果的に
防ぐことができ、キャビテーション等の発生を未然に防
止できる。このため、原子炉内循環ポンプのポンプ効率
の低下やポンプ機器の損傷を未然Kかつ有効的に防止で
きる。
As described above, in the boiling water reactor according to the present invention, partition plates are provided radially in the annular space between the pump parts of the in-reactor circulation pump to divide the lower part of this annular space. The lower part of the space is divided into a plurality of parts along the circumferential direction, and the pump part of the intra-reactor circulation pump is housed in the divided space. Therefore, even if a particular reactor circulation pump stops for some reason, the reactor water flowing down in the annular passage is guided by the partition plate, and the reactor water in the stopped pump section is
Since the fluid is smoothly sucked into the adjacent pump section along the partition plate and beyond the partition plate, it is possible to effectively prevent the generation of vortices and the occurrence of cavitation and the like. Therefore, it is possible to effectively prevent a decrease in pump efficiency of the in-reactor circulation pump and damage to pump equipment.

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

型原子炉を示す縦断面図、第2図は原子炉内循環ポンプ
を備えた従来の沸騰水型原子炉の一部を示す斜視図、第
3図は第2図の1t−tn線に沿う断面図、第4図はこ
の発明に係る沸騰水型原子炉の一実施例を示す縦断面図
、第5図は第4図のv−V線に沿う平断面図、第6図は
第5図に示された部分の斜視図を示す。 加・・・原子炉圧力容器、21・・・炉心732911
部・・・炉心、乙・・・気水分離器、冴・・・蒸気乾燥
器、n・・・制御棒駆動機構、羽・・・環状通路、四・
・・隔壁、加・・・原子炉内循環ポンプ、3工・・・ポ
ンプ部、あ・・・ディフューザ、あ・・・炉水流通口、
40・・・炉心下部、42−・・仕切板。 代理人弁理士 則 近 憲 佑 (ほか1名)第 1 
図 第2図 第3図 第4図 第5図 3 第6図
Figure 2 is a perspective view of a part of a conventional boiling water reactor equipped with an internal circulation pump; Figure 3 is taken along line 1t-tn in Figure 2. 4 is a vertical sectional view showing one embodiment of the boiling water nuclear reactor according to the present invention, FIG. 5 is a plan sectional view taken along line v-V in FIG. 4, and FIG. Figure 3 shows a perspective view of the part shown in the figure; Ka...Reactor pressure vessel, 21...Reactor core 732911
Section: Core, Otsu: Steam-water separator, Sae: Steam dryer, n: Control rod drive mechanism, vane: Annular passage, 4:
...Bulkhead, processing...Reactor circulation pump, 3rd work...Pump section, Ah...Diffuser, Ah...Reactor water flow port,
40... Core lower part, 42-... Partition plate. Representative Patent Attorney Kensuke Chika (and 1 other person) No. 1
Figure 2 Figure 3 Figure 4 Figure 5 Figure 3 Figure 6

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器内に炉心シュラウドを収容し、この
炉心シュラウドと原子炉圧力容器との間に環状の炉水通
路を形成し、この環状通路の下部に設けられた隔壁に複
数の原子炉内循環ポンプのポンプ部を取付けた沸騰水屋
原子炉において、上記原子炉内循環ポンプの各ポンプ部
間の環状空間に、この環状空間の下部を分割する仕切板
を放射状に設けたことを特徴とする沸騰水型原子炉。 2、仕切板は矩形をなし、その下部は隔壁に固定される
一方、仕切板の一側端は炉心シュラウドの外周壁に、反
対側の側端は原子炉圧力容器の内周壁にそれぞれ固定さ
れた特許請求の範囲第1項に記載の沸騰水型原子炉。
[Claims] 1. A reactor core shroud is housed in a reactor pressure vessel, an annular reactor water passage is formed between the reactor core shroud and the reactor pressure vessel, and a reactor water passage is provided at the bottom of the annular passage. In a boiling water reactor in which the pump parts of a plurality of in-reactor circulation pumps are attached to a bulkhead, a partition plate is installed in a radial manner in the annular space between each pump part of the in-reactor circulation pump to divide the lower part of this annular space. A boiling water reactor characterized by being installed in 2. The partition plate has a rectangular shape, and its lower part is fixed to the partition wall, while one end of the partition plate is fixed to the outer circumferential wall of the core shroud, and the opposite side end is fixed to the inner circumferential wall of the reactor pressure vessel. A boiling water nuclear reactor according to claim 1.
JP58214110A 1983-11-16 1983-11-16 Boiling-water type reactor Pending JPS60107596A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58214110A JPS60107596A (en) 1983-11-16 1983-11-16 Boiling-water type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58214110A JPS60107596A (en) 1983-11-16 1983-11-16 Boiling-water type reactor

Publications (1)

Publication Number Publication Date
JPS60107596A true JPS60107596A (en) 1985-06-13

Family

ID=16650396

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58214110A Pending JPS60107596A (en) 1983-11-16 1983-11-16 Boiling-water type reactor

Country Status (1)

Country Link
JP (1) JPS60107596A (en)

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