JPS5862593A - Bwr type reactor - Google Patents
Bwr type reactorInfo
- Publication number
- JPS5862593A JPS5862593A JP56162199A JP16219981A JPS5862593A JP S5862593 A JPS5862593 A JP S5862593A JP 56162199 A JP56162199 A JP 56162199A JP 16219981 A JP16219981 A JP 16219981A JP S5862593 A JPS5862593 A JP S5862593A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pressure vessel
- core
- water
- reactor pressure
- 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.)
- Granted
Links
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structures Of Non-Positive Displacement Pumps (AREA)
- Physical Or Chemical Processes And Apparatus (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】
本発明は炉心再循環ポンｌを備えた沸騰水形原子炉に関
する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a boiling water nuclear reactor equipped with a core recirculation pump.
一般に沸騰水形原子炉ｒｆｉ第１図ないしｓＩ３図に示
す如く構成さ−れてぃる．すなわち、図中１は原子炉圧
力容器であって、この原子炉圧カ容暮１内ＫＦｉシ．ラ
ウド２が設けられている．そして、このシ．ラウｙ２内
Ｋｌｒｌ炉心３が収容されている．そして、この炉心３
の下方ＶｃＦｉ制御棒案内管４・・・が設けられ、これ
らの制御棒案内管４・・・の下端ＫＦｉ制御棒駆動機構
５・・・が接続されており、これらの制御棒駆動機構５
・・・は原子炉圧力容器１０下鏡ｇ６を貫通している。In general, a boiling water reactor RFI is constructed as shown in Figures 1 to 3. That is, numeral 1 in the figure is the reactor pressure vessel, and the KFi shell in the reactor pressure vessel 1. Loud 2 is provided. And this sh. The Klrl reactor core 3 in Rau Y2 is housed. And this core 3
A lower VcFi control rod guide tube 4... is provided, and a lower end KFi control rod drive mechanism 5... of these control rod guide tubes 4... is connected, and these control rod drive mechanisms 5...
... penetrates the lower mirror g6 of the reactor pressure vessel 10.
そして、上記炉心１内で発生した蒸気は炉水とともに気
水分離器ＩＫ送られ、蒸気と炉水とが分離され、分離さ
れ友蒸気は蒸気乾燥−８によって湿分を分離したのち主
蒸気ノズルｔ・・・から主蒸気管を介してタービン（い
ずれも図示せず）Ｋ送られるように構成されている。ｔ
た。気水分離器１で分離された炉水は給水スノ譬−ジャ
１゜から供給される給水とともにシュラウド２の外周面
と原子炉圧力容器１の内周面との間を下方に流れ、炉心
再循環ボン！たとえばインターナル４ング１１・・・に
よって原子炉圧力容器１内下部に送られ、ふ友たび炉心
３内に下方から流入するように構成されている。上記イ
ンターナルポンプ１−１・２−は７．ラウド２と原子炉
圧力容器１との関に設けられ友隔壁１２を貫通して設け
られ友ポング部１３・・・と、原子炉圧力容器１の下ｇ
Ｋ設けられたモータケーシング１４・・・Ｐ３に収容さ
れたモータ１５・・・と、これらモータ１５・・・と−
ンプ部１３・・・とを連結する軸１６・・・とから構成
されている。また、上記イ、ラウド２の下縁部と原子炉
圧力容器１の下鏡ｇ６との関には足部１７・・・が設け
られ、上記シュラウド２ＩＩｉこれら足部１１・・・に
ょって支持されている。こ、れら足部１２・・・はイン
ターナルポンプ１−１・・・間に配置されてお）、これ
ら足部１１・・・間は炉水流通口１８・・・に形成され
ている・そして・上記インターナル４ンｆ１−１・・・
のｆング部１３・・・がら吐出され九炉水はこれら炉水
流通口１８・・・を通って原子炉圧力容器１内下部に送
られるように構成されている。The steam generated in the reactor core 1 is then sent to the steam separator IK together with the reactor water, where the steam and reactor water are separated. t... to a turbine (not shown) K via a main steam pipe. t
Ta. The reactor water separated by the steam separator 1 flows downward between the outer circumferential surface of the shroud 2 and the inner circumferential surface of the reactor pressure vessel 1 together with the supply water supplied from the water supply tank 1, and the reactor core is regenerated. Circulating bong! For example, it is configured to be sent to the lower part of the reactor pressure vessel 1 by internal rings 11, and then to flow into the reactor core 3 from below. The above internal pumps 1-1 and 2- are 7. A companion pump part 13 provided at the junction between the loud 2 and the reactor pressure vessel 1 and penetrating the companion bulkhead 12... and a lower g of the reactor pressure vessel 1.
Motor casing 14 provided in K...motor 15 accommodated in P3, these motors 15... and -
The shaft 16 connects the pump section 13 and the pump section 13. In addition, feet 17 are provided at the junction between the lower edge of the shroud 2 and the lower mirror g6 of the reactor pressure vessel 1, and the shroud 2IIi is supported by these feet 11. has been done. These legs 12... are arranged between the internal pumps 1-1...), and the space between these legs 11... is formed into a reactor water flow port 18...・And the above internal 4n f1-1...
The nine reactor water discharged from the f-ring portions 13 is configured to be sent to the lower part of the reactor pressure vessel 1 through these reactor water flow ports 18.
ところで・上記インターナルポンプ１１・・・は危険速
度を大きくするためできるだけ高い吸込水頭圧を必要と
し、この吸込水頼圧を高めるため下方に設けられている
。このため魁インターナルポング１−１・・・のポング
部Ｊ３・・・から吐出された炉水はあまシ拡散せず、強
い噴流となって炉水流通口１１・・・を通って原子炉圧
力容器１内下Ｓに流入する。このため、この噴流が原子
炉圧力容器１内下部にある制御棒案内管４・・・等に当
０、翻ら制御棒案内管４ 、ｄ！振、Ｌ、、大ヶ応力が
発生して原子炉の寿命を短縮する不具合があった。By the way, the internal pump 11 requires as high a suction head pressure as possible in order to increase the critical speed, and is provided below in order to increase this suction water head pressure. For this reason, the reactor water discharged from the pump parts J3 of the internal pumps 1-1 does not diffuse well, but forms a strong jet and flows through the reactor water flow ports 11 to the reactor. It flows into the lower part S of the pressure vessel 1. For this reason, this jet stream hits the control rod guide tubes 4, etc. located at the lower part of the reactor pressure vessel 1, and the control rod guide tubes 4, d! There was a problem in that large amounts of stress were generated, shortening the life of the reactor.
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インターナル４ング等あ炉心再循環
ポ□ンプから吐出される炉水が強い噴流となって原子炉
圧力容器内下ｔ１５に流入するのを防止し、この原子炉
圧力容器内下部にある部品の振動等を防止して過大な応
力の発生や寿命の短縮等を防止することができる沸騰水
形原子炉を得ることにある。The present invention has been made based on the above circumstances, and its purpose is to cause reactor water discharged from internal four-rings and other core recirculation pumps to form a strong jet and flow down inside the reactor pressure vessel. To obtain a boiling water nuclear reactor that can prevent the occurrence of excessive stress and shortening of life by preventing water from flowing into the reactor pressure vessel and preventing vibrations of parts in the lower part of the reactor pressure vessel. It is in.
すなわち本発明の構成は、７ユラクドの下縁部と原子炉
圧力容器の下鏡部との間に分散整流体を設け、炉心再循
環−ンプから吐出される炉水をこの分散整流体によって
分散し、この炉水が強い噴流やなって原子炉圧力容器内
下部に流入するのを防止するものである。In other words, the configuration of the present invention is that a distributed flow regulator is provided between the lower edge of the reactor pressure vessel and the lower end of the reactor pressure vessel, and the reactor water discharged from the core recirculation pump is dispersed by the distributed flow regulator. This prevents this reactor water from forming a strong jet and flowing into the lower part of the reactor pressure vessel.
次に本発明の詳細な説明する。第４図ないし第６図は本
発明の第１実施例を示す０図中１０１Ｆｉ原子炉圧や容
器であって、この原子ツ圧力容器１０１内ＫＦｉシ、ラ
ウド１０２が設けられている。そして、このシュラウド
１０２内には炉心１０３が収容されている。そして、こ
の炉心１０１の下方には制御棒案内管１０４・・・が設
けられ、これらの制御棒案内管１０４・・・の下端Ｋｉ
ｊ制御棒駆動機構１ｏｔｔ・・・が接続されており、こ
れらの制御棒駆動機構１０５・・・は原子炉圧力容器１
０１の下鏡部１０６を貫通している。そして、上記炉心
１０３内で発生した蒸気は炉水とともに気水分離器１０
１に送られ、蒸気と炉水とが分離され１分離された蒸気
は蒸気乾−器１０１によって湿分を分醸し、たの、ち、
主蒸気ノズル１０９・・・から主蒸気管を介してタービ
ン（いずれも図示せず）Ｋ送られるように構成されてい
る・また、気水分離器で分離された炉水は給水ス／ｌ−
ジャ３７４）から供給される給水とともにシ、ラウＰ１
０２の外周面と原子炉圧力容器１０１の内周面と゛の〒
を下方に流れ、炉心再循環４ンゾたとえば複数のインタ
ーナルポン！に１１・・・によって原子炉圧力容器１０
１内下部に送られ・ふ友たび炉心１０３内に下方から流
入するように構成されている。上記インターナルポンｆ
ｉ Ｉ Ｊ・・・はシュラウド１０２と原子炉圧力容器
１０１との間に設けられ光隔壁１１２を貫通して設けら
れたポンプ部１１３・・・と、原子炉圧力容器１０１の
下＠に設けられたモータケーシング１１４・・・内に収
容されたモータ１１１５・・・と、これらモータ１１５
・・・とｌング部Ｉ Ｊ ｊ ・・・と一連結する軸１
１ｇ’−・□とから構成され、これらインターナルポン
プｘＹ”ｊ・・・ｉ周方向にわたって所定間隔で配列さ
れている。Next, the present invention will be explained in detail. FIGS. 4 to 6 show a first embodiment of the present invention, which shows a nuclear reactor pressure vessel 101 in FIG. A reactor core 103 is housed within this shroud 102 . Control rod guide tubes 104... are provided below this core 101, and the lower ends Ki of these control rod guide tubes 104...
j Control rod drive mechanisms 1ott... are connected, and these control rod drive mechanisms 105... are connected to the reactor pressure vessel 1.
It passes through the lower mirror part 106 of 01. The steam generated in the reactor core 103 is then transferred to the steam-water separator 10 along with the reactor water.
1, steam and reactor water are separated, and the separated steam is separated in moisture by a steam dryer 101.
The main steam nozzle 109 is configured to be sent to a turbine (none of which is shown) via the main steam pipe.Furthermore, the reactor water separated by the steam water separator is supplied to the water supply tank/l-
With the water supply supplied from Ja 374),
The outer peripheral surface of 02 and the inner peripheral surface of the reactor pressure vessel 101 and
Flowing downwards, the core recirculates for example multiple internal pumps! Reactor pressure vessel 10 by 11...
The fuel is sent to the lower part of the reactor core 103 and is configured to flow into the reactor core 103 from below. The above internal pon f
i I J... is provided between the shroud 102 and the reactor pressure vessel 101, and the pump part 113... provided through the optical barrier wall 112, and the pump part 113... provided below the reactor pressure vessel 101. The motors 1115... accommodated in the motor casings 114... and these motors 115...
... and the lug part I J j ... and the shaft 1 that is connected in series with...
1g'-, □, and are arranged at predetermined intervals over the circumferential direction of these internal pumps xY''j...i.
また、上記シュラウド１０２と原子炉圧力容器１０１０
下鏡＠１０ｇとの間には分散整流体１１７・・・が設け
られており、上記７１ラウド１０２はこれら分散整流体
１１１・・・によって支持されている。そして、これら
分散整流体１１１・・・は各インターナルポンプＪ Ｊ
１−・・に対応した位置に上下方向に沿って設けられ
、その断面形状は第５図に示す如く山形をなし、かつそ
の斜面部は凹状に彎曲されている一□七して、これら分
散整流体１１１・・・関すなわちインターナルポンプ１
１１・・・間に対応した部分は炉水流通口１１８・・・
に形成されている。In addition, the shroud 102 and the reactor pressure vessel 1010
A dispersion regulator 117 is provided between the lower mirror @10g, and the 71 loud 102 is supported by these dispersion regulators 111. These distributed regulating fluids 111... are connected to each internal pump JJ.
1-... are provided along the vertical direction at positions corresponding to Fluid regulator 111...in other words, internal pump 1
11... The corresponding part between them is the reactor water flow port 118...
is formed.
次に上記ｊ［１実施例の作用を説明する。原子炉圧力容
器１０１内の炉水は上記のインターナルポンプ１−Ｌｌ
・・・によって強制的に原子炉圧力容器１０１門下部に
送られ、下方から炉心１０１１内に流入する。この場合
、これらインターナル４ンプ１１１・・・の４ンプＮ１
１３・・・から吐出される炉水の噴流は原子炉圧力容器
１０１０下鏡部１０ｉＫ轟って原子炉圧力容器１０１の
中心方向に偏向され、各分散整流体１１１・・・に当る
。Next, the operation of the above j[1 embodiment] will be explained. The reactor water in the reactor pressure vessel 101 is pumped through the internal pump 1-Ll described above.
... is forcibly sent to the lower part of the reactor pressure vessel 101 gate, and flows into the reactor core 1011 from below. In this case, 4 pumps N1 of these 4 internal pumps 111...
The jet of reactor water discharged from the reactor pressure vessel 1010 lower mirror section 10iK is deflected toward the center of the reactor pressure vessel 101, and hits each distributed regulator 111...
□そして、これら分散整流体１１１・・・は断面山形状
ｔなしそいるので炉水の噴流は周方向に分散偏向される
。したがって原子炉圧力容器１０１０下鏡に流入する炉
水は均一に分散され九平均し良識れとなる。よってこの
原子炉圧力容器１０１内下部にある制御棒案内管１０４
・・・が振動するようなことは防止され、過大な応力の
発生や原子炉の痔命の短縮は防止される。なお、この第
１実施例のものは分散整流体１１１・・・の斜面−が凹
状に彎曲しているので炉水が一層均一に分散偏向される
。□Since these distributed regulating fluids 111... have a mountain-shaped cross section t, the jet of reactor water is dispersed and deflected in the circumferential direction. Therefore, the reactor water flowing into the lower mirror of the reactor pressure vessel 1010 is uniformly distributed and has a nine-average ratio, which is common sense. Therefore, the control rod guide tube 104 located in the lower part of the reactor pressure vessel 101
... will be prevented from vibrating, and the generation of excessive stress and shortening of the reactor's lifespan will be prevented. In the first embodiment, since the slopes of the dispersion straighteners 111 are curved in a concave manner, the reactor water is dispersed and deflected more evenly.
なお１本発明は上記の第１実施例には限定されない。Note that the present invention is not limited to the first embodiment described above.
たとえば第７図ないし第９図ｔｔｃｉ１本発明の第２実
施例を示す、この第２１！施例はシュラウド１０２と原
子炉圧力容器１０１の下鏡部１０６との間を閉塞する短
円筒状の分散整流体１１１′を設け、この分散整流体Ｊ
１ ’Ｉ’Ｋ１−４多数の炉水流通口１１８′・・・
全周方向に配列して形成したものである。そして、この
炉水流通口１１８′・・・けインターナル４ンｆ１工Ｌ
１・・・に近い位置にあるものはその開口面積が小さく
、インターナル４ンプ１．Ｌｌ・・・から離れるに従っ
てその開口面積が大となるように構成されている。なお
、このＩＩ２実施例は上記の点以外は前記第１実施伺と
同様の構成で、第７図ないしｔＲ９図中第１実施例に対
応する部分Ｋｌｆｉ同符号同符号管上の説明を省略する
。For example, FIGS. 7 to 9ttci1 show a second embodiment of the present invention, and this 21st! In this embodiment, a short cylindrical distributed regulating fluid 111' that closes the space between the shroud 102 and the lower mirror portion 106 of the reactor pressure vessel 101 is provided, and this distributed regulating fluid J
1 'I'K1-4 Numerous reactor water flow ports 118'...
They are arranged in the circumferential direction. And this reactor water flow port 118'...
Those located close to 1... have a small opening area, and the internal 4 amplifiers 1. The opening area is configured to increase as the distance from Ll... increases. This II2 embodiment has the same configuration as the first embodiment except for the above-mentioned points, and the explanations on the parts Klfi and the same symbols corresponding to the first embodiment in FIGS. 7 to tR9 will be omitted. .
この第２実施例は、各インターナルポンプ、Ｉ Ｊ １
・・・のポンｆ部１１３・・・から吐出された炉水は分
散整流体１１７′の炉水流通口１１８′・・・から分散
して原子炉圧力容器１０１内下！ｌｓ＆を流入し、制御
棒案内管１０４・・・等の振動を防止する。In this second embodiment, each internal pump, I J 1
The reactor water discharged from the pump f section 113... is dispersed from the reactor water flow port 118' of the distributed flow regulator 117' and flows down into the reactor pressure vessel 101! ls& to prevent vibrations of the control rod guide tubes 104, etc.
なお・この第２実施例のものは炉水流通口１１８′・−
・の−口面積がインターナルポンプ１１１・・・から離
れるに従って大となるように構成されているので、原子
炉圧力容器１０１内下部に流入する炉水の流量分布が周
方向にわたってよシ均一となる。Note that this second embodiment has a reactor water flow port 118'.-
Since the opening area of the . Become.
なお１本発明は上記の実施例にも限定されない・
たとえば分散整流体の構成は必らずしも上記の実施例の
４０に限定されず、要は炉水を周方向に分散させるもの
であればどのようなものでもよい。Note that the present invention is not limited to the above embodiments. For example, the configuration of the distributed flow regulator is not necessarily limited to 40 of the above embodiments, and in short, any structure that disperses reactor water in the circumferential direction may be used. It can be anything like that.
また・分散整流体は必゛らずしもシュラウドの支持を兼
用するものに限らず、シュラウドを支持する部材を別に
設けてもよい。Furthermore, the distributed fluid regulating device is not necessarily limited to one that also serves as support for the shroud, and a member that supports the shroud may be provided separately.
さらに炉心循ｆｌ１１ｆ！ンプは必らずしもインターナ
ルポンプに＠らず％ジェ會トポンプであってもよい。Furthermore, core circulation fl11f! The pump is not necessarily an internal pump, but may be a jet pump.
上述の如く本発明はシュラウドの下縁部と原子炉圧力容
器の下鏡部との間に炉心循環ポンプから吐出される炉水
の流れを周方向に分−散する分散整流体を設けたもので
ある。したがって、炉心循環ｌンプから吐出される炉水
の噴流はこの分散整流体によって局方向に分散され、原
子炉容器内下部にある部品に強い噴流が幽るのが防止さ
れ、これら部品が振動することはない。As described above, the present invention provides a distributed flow regulator that disperses the flow of reactor water discharged from the core circulation pump in the circumferential direction between the lower edge of the shroud and the lower head of the reactor pressure vessel. It is. Therefore, the jet of reactor water discharged from the core circulation pump is dispersed in the local direction by this dispersion regulating fluid, preventing a strong jet from falling on parts located in the lower part of the reactor vessel, and causing these parts to vibrate. Never.
よってこれら部品に過大な応力が発生することはなく、
また疲労等により原子炉の痔命を短縮することがない等
その効果は大である。Therefore, excessive stress is not generated in these parts,
Moreover, the effect is great, as it does not shorten the life of the nuclear reactor due to fatigue or the like.
第１図ないし第３図は従来例を示し、第１図は縦断面図
、第２図ＦｉＭＩ図のＩ−１！ｉＫ沿う断面図、第３図
はｍ２図の１１矢視図である。
第４図ないし第６図は本発明の第１１！施例を示し６、
ｗ！４図は縦断面図、第５１９ｐＦｉ第４図のｙ−■Ｉ
ＩＫ沿う断面図、第６図＃ｉ第５図のＷ−■矢視図であ
る。第７図ないし８１９図は本発明の第２実施例を示し
、第７図は縦断面図、＃１８図は［７図の■−■線に沿
う断面図、縞９図は第８図のに−ＩＫ矢視図である。
１０１・・・原子炉圧力容器・１０１・・・Ｖ、ラクト
、１０１・・・炉心、１０４・・・制御棒案内管、１０
６・・・下鏡ｇ％ Ｊ工Ｌ１・・・インターナルポンプ
（炉心再循環４ング）、Ｊ Ｉ ７ 、 Ｊ Ｊ ７’
・・・分散偏向体、Ｊ Ｊ １１ 、 Ｊ １ ＆’・
・・炉水流通口。
出願人代場人 片場上 軸 江 武 崖第１図
第２図
第４図
第５図
第７図
第８図1 to 3 show a conventional example, in which FIG. 1 is a vertical sectional view and FIG. 2 is a FiMI diagram I-1! The sectional view taken along the iK line, FIG. 3, is a view taken along the arrow 11 of the m2 diagram. Figures 4 to 6 are the eleventh example of the present invention! Showing examples 6,
Lol! Figure 4 is a vertical cross-sectional view, 519pFi Figure 4 y-■I
It is a sectional view taken along IK, and a view taken along arrow W-■ in FIG. 6 and #i in FIG. 7 to 819 show the second embodiment of the present invention, FIG. 7 is a longitudinal sectional view, FIG. 18 is a sectional view taken along the line ■-■ in FIG. -IK arrow view. 101...Reactor pressure vessel, 101...V, lacto, 101...Reactor core, 104...Control rod guide tube, 10
6... Lower mirror g% J engineering L1... Internal pump (core recirculation 4 rings), J I 7, J J 7'
... Dispersion deflector, J J 11 , J 1 &'
・Reactor water flow port. Applicant on behalf of the applicant Katabajo Jiku Emu Cliff Figure 1 Figure 2 Figure 4 Figure 5 Figure 7 Figure 8
Claims (3)
、。 内に設けられ友り、ラウドと、このシュラクト内に収容
された炉心と：上記シ、′ラウドの外周面と原子炉圧力
容−の内−局面との間に設けられた複数の炉心再循Ｉｌ
ｌ／ングとを備えたものにおいて、上記シュラウドの下
縁部と上記原子炉圧力容器の下鏡部との間に上記炉心再
循環？ン！から吐出される炉水を周方向に分散する分散
整流体とを具備したことを特徴とする沸騰水形原子炉。(1) *+ts8E, 1*ts'h', Yu. Wow, 1 ka. a reactor core housed in the shract; Il
In the reactor core recirculation system, the core recirculation is provided between the lower edge of the shroud and the lower head of the reactor pressure vessel. hmm! What is claimed is: 1. A boiling water nuclear reactor characterized by comprising a dispersion regulating fluid for distributing reactor water discharged from the reactor in a circumferential direction.
応して設けられ前記炉心再循環ポンｆ−１）、ら吐出さ
れる炉水を周方向に偏向させる断面山形状のものである
ことＹｒ％徴とする前記特許請求の範囲第１項記載の沸
騰水形原子炉。(2) The distributed flow regulator is provided corresponding to the core recirculation pump and has a mountain-shaped cross section that deflects reactor water discharged from the core recirculation pump f-1) in the circumferential direction. A boiling water nuclear reactor according to claim 1, wherein the boiling water reactor is expressed as a percentage.
原子炉圧力容器の下鏡部との間を閉塞して設けられると
と４に周方向にわたって配列された多数の炉水流通口を
有するものであることを特徴とする特許 騰水形原子炉。(3) The distributed flow regulator is provided by closing the space between the lower edge of the 71 loud and the lower head of the reactor pressure vessel. A patented rising water reactor characterized by having the following characteristics:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56162199A JPS5862593A (en) | 1981-10-12 | 1981-10-12 | Bwr type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56162199A JPS5862593A (en) | 1981-10-12 | 1981-10-12 | Bwr type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5862593A true JPS5862593A (en) | 1983-04-14 |
| JPS6149637B2 JPS6149637B2 (en) | 1986-10-30 |
Family
ID=15749864
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56162199A Granted JPS5862593A (en) | 1981-10-12 | 1981-10-12 | Bwr type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5862593A (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5566795A (en) * | 1978-11-13 | 1980-05-20 | Tokyo Shibaura Electric Co | Control device for flow rate of reactor coolant |
-
1981
- 1981-10-12 JP JP56162199A patent/JPS5862593A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5566795A (en) * | 1978-11-13 | 1980-05-20 | Tokyo Shibaura Electric Co | Control device for flow rate of reactor coolant |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6149637B2 (en) | 1986-10-30 |
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