JPH0119115B2 - - Google Patents
Info
- Publication number
- JPH0119115B2 JPH0119115B2 JP55180955A JP18095580A JPH0119115B2 JP H0119115 B2 JPH0119115 B2 JP H0119115B2 JP 55180955 A JP55180955 A JP 55180955A JP 18095580 A JP18095580 A JP 18095580A JP H0119115 B2 JPH0119115 B2 JP H0119115B2
- Authority
- JP
- Japan
- Prior art keywords
- steam
- steam dryer
- pressure vessel
- reactor pressure
- reactor
- 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
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 17
- 230000007246 mechanism Effects 0.000 claims description 14
- 238000009835 boiling Methods 0.000 claims description 8
- 230000002093 peripheral effect Effects 0.000 claims description 4
- 238000007789 sealing Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 2
- 230000005514 two-phase flow Effects 0.000 description 1
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
- 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に関する。[Detailed description of the invention] The present invention relates to boiling water nuclear reactors.
一般に沸騰水形原子炉は炉心で発生した蒸気と
水の二相流を気水分離器で水と蒸気とに分離し、
分離した蒸気はさらに蒸気乾燥器によつて湿分が
除去されて乾き蒸気となり、タービンへ送られる
ように構成されている。そして、従来の沸騰水形
原子炉はたとえば第１図の如く構成されていた。
すなわち、１は原子炉圧力容器であつて、その上
端には上蓋２が取付けられている。そして、この
原子炉圧力容器１内には炉心３が収容されてい
る。そしてこの炉心３の下方には多数の制御棒案
内管４…が設けられている。また、これら制御棒
案内管４…の下端には制御棒駆動機構ハウジング
５…が接続され、これらの制御棒駆動機構ハウジ
ング５は原子炉圧力容器１の底壁部を貫通して外
部に導出されている。そしてこれら制御棒駆動機
構ハウジング５…の下端部にはそれぞれ制御棒駆
動機構６…が設けられている。また、上記炉心３
の上方には気水分離器７が設けられている。そし
てこの気水分離器７は炉心３を囲繞するシユラウ
ド８のシユラウドヘツド９に取付けられている。
さらに、この気水分離器７の上方には蒸気乾燥器
１０が設けられている。そして、この蒸気乾燥器
１０の下端部外周には蒸気乾燥器支持環１１が設
けられている。そして、原子炉圧力容器１の内周
面には蒸気乾燥器支持ブラケツト１２が突設され
ており、上記蒸気乾燥器支持環１１はこの蒸気乾
燥器支持ブラケツト１２上に載置され、蒸気乾燥
器１０を支持している。また、この蒸気乾燥器１
０の上面にはこれを吊り上げるための蒸気乾燥器
吊上部材１３…が設けられている。そして上記原
子炉圧力容器１の上蓋２の内面には蒸気乾燥器押
えブラケツト１４…が突設されており、これら蒸
気乾燥器押えブラケツト１４…は蒸気乾燥器１０
の蒸気乾燥器吊上部材１３…の上面に当接し、こ
の蒸気乾燥器１０を押圧固定している。そして、
このような原子炉は定期点検時等において炉心３
に装荷されている核燃料を交換する場合には、ま
ず上蓋２を取外し、次に蒸気乾燥器吊上部材１３
…に吊上具等を接続してこの蒸気乾燥器１０を吊
り上げて取外し、さらにシユラウドヘツド９を取
外し、気水分離器７をこのシユラウドヘツド９と
ともに吊上げて取外していた。 In general, boiling water reactors separate the two-phase flow of steam and water generated in the reactor core into water and steam using a steam separator.
The separated steam is further configured to have moisture removed by a steam dryer to become dry steam, and to be sent to the turbine. A conventional boiling water nuclear reactor was constructed as shown in FIG. 1, for example.
That is, 1 is a nuclear reactor pressure vessel, and an upper cover 2 is attached to its upper end. A reactor core 3 is housed within this reactor pressure vessel 1 . A large number of control rod guide tubes 4 are provided below this core 3. Control rod drive mechanism housings 5 are connected to the lower ends of these control rod guide tubes 4, and these control rod drive mechanism housings 5 penetrate the bottom wall of the reactor pressure vessel 1 and are led out. ing. Control rod drive mechanisms 6 are provided at the lower ends of these control rod drive mechanism housings 5, respectively. In addition, the core 3
A steam/water separator 7 is provided above. This steam separator 7 is attached to a shroud head 9 of a shroud 8 surrounding the reactor core 3.
Furthermore, a steam dryer 10 is provided above the steam separator 7. A steam dryer support ring 11 is provided on the outer periphery of the lower end of this steam dryer 10. A steam dryer support bracket 12 is protruded from the inner circumferential surface of the reactor pressure vessel 1, and the steam dryer support ring 11 is placed on this steam dryer support bracket 12. 10 is supported. In addition, this steam dryer 1
A steam dryer lifting member 13 for lifting the dryer is provided on the upper surface of the dryer. Steam dryer holding brackets 14 are protruded from the inner surface of the upper cover 2 of the reactor pressure vessel 1, and these steam dryer holding brackets 14...
The steam dryer 10 is pressed and fixed by contacting the upper surface of the steam dryer lifting member 13 . and,
In such reactors, core 3 is
When replacing the nuclear fuel loaded in the steam dryer, first remove the upper cover 2, and then remove the
The steam dryer 10 was lifted and removed by connecting a lifting tool or the like to..., the shroud head 9 was removed, and the steam/water separator 7 was lifted together with the shroud head 9 and removed.
また、第２図には従来の他の形式の沸騰水形原
子炉を示す。このものは上方から炉心内に制御棒
を挿入する形式のものであつて、炉心１０３の上
方に制御棒案内管１０４…が設けられている。そ
してこれら制御棒案内管１０４…の上端部には制
御棒駆動機構ハウジング１０５…が接続され、こ
れらの制御棒駆動ハウジング１０５は原子炉圧力
容器１０１の上蓋１０２を貫通して設けられてお
り、これらの制御棒駆動ハウジング１０５…の上
端部にはそれぞれ制御棒駆動機構１０６…が設け
られている。また、このものでは蒸気乾燥器１１
０は環状をなしており、上記制御棒駆動機構ハウ
ジング１０５…はこの蒸気乾燥器１１０内に挿入
され、また気水分離器１０７を貫通して配置され
ている。そして、この蒸気乾燥器１１０の下部外
周には前記のものと同様に蒸気乾燥器支持環１１
１が設けられており、この蒸気乾燥器支持環１１
１は原子炉圧力容器１０１の内面に設けられた蒸
気乾燥器支持ブラケツト１１２…上に当接して蒸
気乾燥器１１０を支持している。また、上記の蒸
気乾燥器１１０の上面には蒸気乾燥器吊上部材１
１３…が設けられている。そして上蓋１０２の内
周面には蒸気乾燥器押えブラケツト１１４…が突
設され、これらの蒸気乾燥器押えブラケツト１１
４…は蒸気乾燥器吊上部材１１３…の上面に当接
して蒸気乾燥器１１０を押圧固定している。また
蒸気乾燥器１１０の外周と原子炉圧力容器１０１
の内周面との間の間隔はシール部材１１５によつ
て閉塞されており、蒸気が蒸気乾燥器１１０を通
らずにこの間隙を通つて直接主蒸気ノズル１１
６，１１６に流れるのを防止している。そして、
このような原子炉においても核燃料の交換等をな
す際には前記の原子炉と同様に上蓋１０２、蒸気
乾燥器１１０および気水分離器１０７をそれぞれ
別々に取外すものとなる。 FIG. 2 also shows another type of conventional boiling water reactor. This is of a type in which control rods are inserted into the reactor core from above, and control rod guide tubes 104 are provided above the reactor core 103. Control rod drive mechanism housings 105 are connected to the upper ends of these control rod guide tubes 104, and these control rod drive housings 105 are provided through the upper cover 102 of the reactor pressure vessel 101. Control rod drive mechanisms 106 are provided at the upper ends of the control rod drive housings 105, respectively. Also, in this one, the steam dryer 11
0 has an annular shape, and the control rod drive mechanism housing 105 is inserted into the steam dryer 110 and is arranged to pass through the steam separator 107. A steam dryer support ring 11 is provided on the outer periphery of the lower part of this steam dryer 110 in the same manner as described above.
1 is provided, and this steam dryer support ring 11
1 supports the steam dryer 110 by coming into contact with a steam dryer support bracket 112 provided on the inner surface of the reactor pressure vessel 101. Further, a steam dryer lifting member 1 is provided on the upper surface of the steam dryer 110.
13... are provided. Steam dryer press brackets 114 are protruded from the inner peripheral surface of the upper lid 102, and these steam dryer press brackets 11
4... contact the upper surface of the steam dryer lifting member 113... to press and fix the steam dryer 110. In addition, the outer periphery of the steam dryer 110 and the reactor pressure vessel 101
The gap between the inner circumferential surface of the main steam nozzle 11 and the inner circumferential surface of the
6,116. and,
In such a nuclear reactor, when exchanging nuclear fuel, etc., the upper cover 102, steam dryer 110, and steam separator 107 are each removed separately, as in the above-mentioned nuclear 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、蒸気乾燥器を原子
炉圧力容器の上蓋と一体に取外すことができると
ともに、蒸気乾燥器と原子炉圧力容器との間をシ
ール部材でシールする必要がなく、炉心で発生し
た全ての蒸気を蒸気乾燥器を通過させて主蒸気ノ
ズルへ導く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 enable the steam dryer to be removed integrally with the upper cover of the reactor pressure vessel, and to connect the steam dryer and the reactor pressure vessel. To provide a boiling water nuclear reactor in which all steam generated in a reactor core can pass through a steam dryer and be guided to a main steam nozzle without the need for sealing between the gaps with a sealing member.
以下本発明を図面に示す実施例にしたがつて説
明する。 The present invention will be described below with reference to embodiments shown in the drawings.
第３図は本発明の一実施例を示し、図中３０１
は原子炉圧力容器であつて、その上端には上蓋３
０２が取付けられている。そして、この原子炉圧
力容器３０１内下部にはシユラウド３０８が設け
られており、このシユラウド３０８内には炉心３
０３が収容されている。また、この炉心３０３の
上方には多数の制御棒案内管３０４…が設けられ
ている。そしてこれらの制御棒案内管３０４の上
端部にはそれぞれ制御棒駆動機構ハウジング３０
５…が接続され、これらの制御棒駆動機構ハウジ
ング３０５…は制御棒駆動機構３０６…が設けら
れている。また、上記制御棒案内管３０４…の上
方には気水分離器３０７が設けられており、この
気水分離器３０７は上記シユラウド３０８の上端
に取付けられたシユラウドヘツド３０９に取付け
られている。また、この気水分離器３０７の上方
には蒸気乾燥器３１０が設けられている。この蒸
気乾燥器３１０は環状をなしており、上記制御棒
駆動機構ハウジング３０５…はこの蒸気乾燥器３
１０内に挿通され、また上記気水分離器３０７内
を貫通している。そして、この蒸気乾燥器３１０
の下端部外周には蒸気乾燥器支持環３１１が設け
られている。また、上記原子炉圧力容器３０１の
内周面には蒸気乾燥器支持ブラケツト３１２が設
けられている。そして上記蒸気乾燥器支持環３１
１は上記の蒸気乾燥器支持ブラケツト３１２上に
当接し、この蒸気乾燥器３１０を支持している。
そして、蒸気蒸気乾燥器３１０の上端には蒸気乾
燥器取付部材３１３が設けられている。この蒸気
乾燥器取付部材３１３は円筒状をなし、その上端
部全周は前記上蓋３０２の内面に固定されてい
る。なお、３１４，３１４は主蒸気ノズルであ
る。 FIG. 3 shows an embodiment of the present invention, in which 301
is a reactor pressure vessel, and there is a top cover 3 at its upper end.
02 is installed. A shroud 308 is provided in the lower part of the reactor pressure vessel 301, and a reactor core 308 is provided in the shroud 308.
03 is accommodated. Further, a large number of control rod guide tubes 304 are provided above the core 303. A control rod drive mechanism housing 30 is provided at the upper end of each of these control rod guide tubes 304.
5... are connected, and these control rod drive mechanism housings 305... are provided with control rod drive mechanisms 306... Further, a steam/water separator 307 is provided above the control rod guide tubes 304 . . . , and this steam/water separator 307 is attached to a shroud head 309 attached to the upper end of the shroud 308 . Furthermore, a steam dryer 310 is provided above the steam/water separator 307. This steam dryer 310 has an annular shape, and the control rod drive mechanism housing 305...
10 and also passes through the steam/water separator 307. And this steam dryer 310
A steam dryer support ring 311 is provided on the outer periphery of the lower end. Further, a steam dryer support bracket 312 is provided on the inner peripheral surface of the reactor pressure vessel 301. and the steam dryer support ring 31
1 abuts on the steam dryer support bracket 312 and supports this steam dryer 310.
A steam dryer mounting member 313 is provided at the upper end of the steam dryer 310. This steam dryer mounting member 313 has a cylindrical shape, and its entire upper end is fixed to the inner surface of the upper lid 302. Note that 314, 314 are main steam nozzles.
このように、蒸気乾燥器３１０の下部外周にそ
の下端が原子炉圧力容器３０１の内面に設けられ
た環状の蒸気乾燥器支持ブラケツト３１２に当接
する蒸気乾燥器支持環３１１を設けるとともに、
蒸気乾燥器３１０の上部に円筒状の蒸気乾燥器取
付部材３１３を設け、この取付部材３１３の上端
部全周を上蓋３０２の内面に固定することによ
り、蒸気乾燥器３１０の外周と原子炉圧力容器３
０１内面との間隙が閉塞されるため、シール部材
が不要となる。 In this way, a steam dryer support ring 311 is provided on the outer periphery of the lower part of the steam dryer 310, and the lower end thereof abuts on the annular steam dryer support bracket 312 provided on the inner surface of the reactor pressure vessel 301.
A cylindrical steam dryer mounting member 313 is provided on the top of the steam dryer 310, and the entire upper end of this mounting member 313 is fixed to the inner surface of the upper lid 302, thereby connecting the outer periphery of the steam dryer 310 and the reactor pressure vessel. 3
Since the gap with the inner surface of 01 is closed, a sealing member is not required.
上述の如く本発明は、原子炉圧力容器と、この
原子炉圧力容器内に設けられた炉心と、この炉心
の上方に設けられた気水分離器と、この気水分離
器の上方に設けられた環状の蒸気乾燥器と、前記
原子炉圧力容器に設けられ前記蒸気乾燥器を通過
した蒸気を原子炉圧力容器外へ導出する主蒸気ノ
ズルと、前記蒸気乾燥器の中空部を通して制御棒
を前記炉心内に上方より挿入する制御棒駆動機構
とを具備した沸騰水形原子炉において、前記蒸気
乾燥器の下端部外周に蒸気乾燥器支持環を設ける
とともに、この蒸気乾燥器支持環を下方より支持
する蒸気乾燥器支持ブラケツトを前記主蒸気ノズ
ルの下方位置の原子炉圧力容器内面全周に設け、
かつ前記蒸気乾燥器の上端周縁部を円筒状の蒸気
乾燥器取付部材を介して前記原子炉圧力容器の上
蓋内面に固定したので、蒸気乾燥器を原子炉圧力
容器の上蓋と一体に取外すことができるととも
に、蒸気乾燥器と原子炉圧力容器との間をシール
部材でシールする必要がなく、炉心で発生した全
ての蒸気を蒸気乾燥器を通過させて主蒸気ノズル
へ導くことができる沸騰水形原子炉を提供でき
る。 As described above, the present invention includes a reactor pressure vessel, a reactor core provided in the reactor pressure vessel, a steam separator provided above the core, and a reactor core provided above the reactor pressure vessel. a main steam nozzle that is provided in the reactor pressure vessel and guides the steam that has passed through the steam dryer out of the reactor pressure vessel; In a boiling water nuclear reactor equipped with a control rod drive mechanism that is inserted into the reactor core from above, a steam dryer support ring is provided around the outer periphery of the lower end of the steam dryer, and this steam dryer support ring is supported from below. A steam dryer support bracket is provided around the entire inner surface of the reactor pressure vessel below the main steam nozzle,
In addition, since the upper end peripheral portion of the steam dryer is fixed to the inner surface of the upper lid of the reactor pressure vessel via the cylindrical steam dryer mounting member, the steam dryer can be removed together with the upper lid of the reactor pressure vessel. In addition, there is no need to use a sealing member between the steam dryer and the reactor pressure vessel, and all steam generated in the reactor core can pass through the steam dryer and be guided to the main steam nozzle. We can provide nuclear reactors.
第１図は従来例の縦断面図、第２図は他の従来
例の縦断面図、第３図は本発明の一実施例の縦断
面図である。
３０１…原子炉圧力容器、３０２…上蓋、３０
３…炉心、３０５…制御棒駆動機構ハウジング、
３０７…気水分離器、３１０…蒸気乾燥器、３１
３…蒸気乾燥器取付部材。
FIG. 1 is a vertical cross-sectional view of a conventional example, FIG. 2 is a vertical cross-sectional view of another conventional example, and FIG. 3 is a vertical cross-sectional view of an embodiment of the present invention. 301...Reactor pressure vessel, 302...Upper lid, 30
3...Reactor core, 305...Control rod drive mechanism housing,
307...Steam water separator, 310...Steam dryer, 31
3...Steam dryer mounting member.
Claims (1)
設けられた炉心と、この炉心の上方に設けられた
気水分離器と、この気水分離器の上方に設けられ
た環状の蒸気乾燥器と、前記原子炉圧力容器に設
けられ前記蒸気乾燥器を通過した蒸気を原子炉圧
力容器外へ導出する主蒸気ノズルと、前記蒸気乾
燥器の中空部を通して制御棒を前記炉心内に上方
より挿入する制御棒駆動機構とを具備した沸騰水
形原子炉において、前記蒸気乾燥器の下端部外周
に蒸気乾燥器支持環を設けるとともに、この蒸気
乾燥器支持環を下方より支持する蒸気乾燥器支持
ブラケツトを前記主蒸気ノズルの下方位置の原子
炉圧力容器内面全周に設け、かつ前記蒸気乾燥器
の上端周縁部を円筒状の蒸気乾燥器取付部材を介
して前記原子炉圧力容器の上蓋内面に固定したこ
とを特徴とする沸騰水形原子炉。1. A reactor pressure vessel, a reactor core installed within the reactor pressure vessel, a steam separator installed above the core, and an annular steam dryer installed above the steam separator. a main steam nozzle that is provided in the reactor pressure vessel and guides the steam that has passed through the steam dryer out of the reactor pressure vessel; and a control rod is inserted into the reactor core from above through a hollow part of the steam dryer. In a boiling water nuclear reactor equipped with a control rod drive mechanism, a steam dryer support ring is provided around the outer periphery of the lower end of the steam dryer, and a steam dryer support bracket that supports the steam dryer support ring from below. is provided all around the inner surface of the reactor pressure vessel below the main steam nozzle, and the upper end peripheral edge of the steam dryer is fixed to the inner surface of the upper lid of the reactor pressure vessel via a cylindrical steam dryer mounting member. A boiling water reactor characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55180955A JPS57104888A (en) | 1980-12-20 | 1980-12-20 | Bwr type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55180955A JPS57104888A (en) | 1980-12-20 | 1980-12-20 | Bwr type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57104888A JPS57104888A (en) | 1982-06-30 |
| JPH0119115B2 true JPH0119115B2 (en) | 1989-04-10 |
Family
ID=16092191
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55180955A Granted JPS57104888A (en) | 1980-12-20 | 1980-12-20 | Bwr type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57104888A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5075074A (en) * | 1990-05-29 | 1991-12-24 | General Electric Company | Steam-water separating system for boiling water nuclear reactors |
| JP4908012B2 (en) * | 2006-02-23 | 2012-04-04 | 日本原子力発電株式会社 | Boiling water reactor |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS53141889A (en) * | 1977-05-16 | 1978-12-11 | Asea Atom Ab | Steam drier for boiling water reactor |
| JPS5596495A (en) * | 1979-01-17 | 1980-07-22 | Tokyo Shibaura Electric Co | Steam dryer housing |
-
1980
- 1980-12-20 JP JP55180955A patent/JPS57104888A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS53141889A (en) * | 1977-05-16 | 1978-12-11 | Asea Atom Ab | Steam drier for boiling water reactor |
| JPS5596495A (en) * | 1979-01-17 | 1980-07-22 | Tokyo Shibaura Electric Co | Steam dryer housing |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57104888A (en) | 1982-06-30 |
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