JPS6316295A - Earthquakeproof supporter for nuclear reactor built-in type wet motor pump - Google Patents
Earthquakeproof supporter for nuclear reactor built-in type wet motor pumpInfo
- Publication number
- JPS6316295A JPS6316295A JP61159766A JP15976686A JPS6316295A JP S6316295 A JPS6316295 A JP S6316295A JP 61159766 A JP61159766 A JP 61159766A JP 15976686 A JP15976686 A JP 15976686A JP S6316295 A JPS6316295 A JP S6316295A
- Authority
- JP
- Japan
- Prior art keywords
- casing
- gap
- pump
- reactor
- pressure vessel
- 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
Links
- 239000010935 stainless steel Substances 0.000 claims description 8
- 229910001220 stainless steel Inorganic materials 0.000 claims description 8
- 241000196324 Embryophyta Species 0.000 description 12
- 230000007797 corrosion Effects 0.000 description 6
- 238000005260 corrosion Methods 0.000 description 6
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 4
- 229910000975 Carbon steel Inorganic materials 0.000 description 3
- 239000010962 carbon steel Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010586 diagram Methods 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
- Structures Of Non-Positive Displacement Pumps (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】
[発明の目的]
(産業上の利用分野)
本発明は原子炉内蔵型ウェットモータポンプの耐震支持
装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to an earthquake-resistant support device for a wet motor pump built into a nuclear reactor.
(従来の技術)
原子炉内蔵型ウェットモータポンプは通常インターナル
ポンプと呼ばれているが、このインターナルポンプは原
子炉圧力容器の底部に据え付けられており、冷却材であ
る炉水を炉心へ供恰するように構成されている。(Prior technology) A reactor built-in wet motor pump is usually called an internal pump, and this internal pump is installed at the bottom of the reactor pressure vessel and supplies reactor water, which is a coolant, to the reactor core. It is configured to serve.
このようなインターナルポンプの従来例を第3図を参照
しながら説明する。同図において、冷却材である炉水を
駆動するポンプインペラ2は炉内に配設され、ポンプシ
ャフト8を介してウェットモータ部10と接続されてい
る。そして、このポンプシャフト80大部分及びウェッ
トモータ部10はモータケーシング9の中に内蔵されて
おり、このケーシング9のケーシングネック部4はその
付は根部3で原子炉圧力容器のノズル部と溶接構造で結
合されている。A conventional example of such an internal pump will be explained with reference to FIG. In the figure, a pump impeller 2 for driving reactor water, which is a coolant, is disposed inside the reactor and connected to a wet motor section 10 via a pump shaft 8. Most of the pump shaft 80 and the wet motor section 10 are housed in a motor casing 9, and the casing neck section 4 of the casing 9 has a root section 3 which is welded to the nozzle section of the reactor pressure vessel. are combined with.
したがって、インターナルポンプはケーシング付は根部
3を固定端としだ片持梁@造を有しているので、過大な
振動が発生した際にはケーシング付は根部3の応力が大
ぎくなる性質を有している。Therefore, since the internal pump with a casing has a cantilever structure with the root 3 as a fixed end, the stress in the root 3 of the casing will increase when excessive vibration occurs. have.
このケーシング付は根部3の応力を低減させるために、
ケーシングネック部4あるいは原子炉圧力容器外壁下部
から下方に伸びたスリーブ7に係止部5を設けている。With this casing, in order to reduce the stress on the root part 3,
A locking portion 5 is provided on a sleeve 7 extending downward from the casing neck portion 4 or the lower part of the outer wall of the reactor pressure vessel.
この係止部5は常温で嵌め合い構造をなしているが、原
子炉の通常運転時には微小な間隙が生じるように構成さ
れている。ところで、地震時にケーシング9が大きな横
ゆれを生じた場合には上記間隙を越えて係止部5で接触
が発生するようになる。その結果、ケーシング9の撮動
を抑制することになり、応力的に最も厳しい個所である
ケーシング付は根部3に加わるモーメント、応力等を低
減することができる。なお、係止部5は第4図に示すよ
うに、原子炉圧力容器外壁下部から下方に伸びたスリー
ブ7に設けたものも上記第3図と同様にモーメント、応
力等を低減させることができる。この係止部5の間隙と
地震時にケーシング付は根部3に発生し得る最大応力の
間には第5図に示すような路線形の関係にある。This locking portion 5 has a fitting structure at room temperature, but is configured so that a minute gap is created during normal operation of the nuclear reactor. By the way, if the casing 9 undergoes a large lateral vibration during an earthquake, contact will occur at the locking portion 5 across the above-mentioned gap. As a result, the movement of the casing 9 is suppressed, and the moment, stress, etc. applied to the root portion 3 of the casing, which is the most stressed part, can be reduced. As shown in FIG. 4, the locking portion 5 provided on a sleeve 7 extending downward from the lower part of the outer wall of the reactor pressure vessel can also reduce moment, stress, etc. in the same way as shown in FIG. 3 above. . There is a linear relationship between the gap between the locking portions 5 and the maximum stress that can occur in the root portion 3 of the casing during an earthquake, as shown in FIG.
しかして、従来の係止部はケーシング及び原子炉圧力容
器スリーブと同じ炭素鋼(SFVV3)で形成されてい
るため、プラント寿命中に表面腐食、錆等の発生する恐
れがあり、万一、このような腐食。However, because conventional locking parts are made of the same carbon steel (SFVV3) as the casing and reactor pressure vessel sleeve, there is a risk of surface corrosion, rust, etc. occurring during the life of the plant. Like corrosion.
錆等が発生すると上記間隙はプラント運転初期の間隙よ
り大きくなる。例えば、プラント寿命の初期間隙と同等
の腐食による間隙が生じた場合、ケーシング側、原子炉
圧力容器外部スリーブ側のどちらも考慮すると、上記間
隙はプラント寿命末期にはプラント寿命初期の3倍とな
り、ケーシング付は根部に発生し得る応力も3倍となる
。これは係止部の耐震機能が著しい低下することをを意
味している。そして、上記間隙がプラント運転中に拡大
することがなく、一定に保たれる事がインターナルポン
プの支持装置が有効に働く上で、極めて重要となる。When rust or the like occurs, the gap becomes larger than the gap at the initial stage of plant operation. For example, if a gap equal to the gap at the beginning of the plant life occurs due to corrosion, considering both the casing side and the reactor pressure vessel outer sleeve side, the gap at the end of the plant life will be three times the gap at the beginning of the plant life. With a casing, the stress that can occur at the root is also tripled. This means that the earthquake resistance function of the locking portion is significantly reduced. It is extremely important for the internal pump support device to function effectively that the gap does not expand during plant operation and remains constant.
(発明が解決しようとする問題点)
本発明は上記事情に鑑みてなされたもので、その目的は
、プラント運転中にポンプケーシングネック部あるいは
原子炉圧力容器外壁下部から下方に伸びたスリーブに設
けた係止部間隙が腐食等により拡大することがないよう
な原子炉内蔵型つエツトモータポンプの耐震支持装置を
提供することにある。(Problems to be Solved by the Invention) The present invention has been made in view of the above-mentioned circumstances, and its purpose is to install a pump in a sleeve extending downward from the pump casing neck or the lower part of the outer wall of the reactor pressure vessel during plant operation. It is an object of the present invention to provide an earthquake-resistant support device for a jet motor pump built into a nuclear reactor, in which the gap between the locking parts does not expand due to corrosion or the like.
[発明の構成]
(問題点を解決するための手段)
上記目的を達成するために、本発明は、原子炉圧力容器
外壁下部から下方に伸びたスリーブと前記原子炉圧力容
器外壁下部に取付けられたポンプケーシングとの間に間
隙を有するように配置された原子炉内蔵型ウェットモー
タポンプにおいて、前記ポンプケーシングのネック部に
ステンレス鋼製の係止部をリング状全周または数ケ所溶
接するとともに前記係止部に対向する前記スリーブの当
り面にステンレス鋼を溶接したことを特徴とするもので
ある。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention includes a sleeve extending downward from the lower part of the outer wall of the reactor pressure vessel and a sleeve attached to the lower part of the outer wall of the reactor pressure vessel. In a wet motor pump built into a nuclear reactor, which is arranged so as to have a gap between the pump casing and the pump casing, stainless steel locking parts are welded to the neck part of the pump casing in a ring shape around the entire circumference or in several places. It is characterized in that stainless steel is welded to the abutment surface of the sleeve that faces the locking portion.
(作 用)
本発明の原子炉内蔵型ウェットモータポンプの耐震支持
装置によると、ポンプケーシングネック−部あるいは原
子炉圧力容器外壁下部から下方に伸びたスリーブに設け
た係止部とその当り面にステンレス鋼を用いているので
、プラント運転中腐食。(Function) According to the seismic support device for a wet motor pump built into a nuclear reactor of the present invention, the locking portion provided on the sleeve extending downward from the pump casing neck portion or the lower part of the outer wall of the reactor pressure vessel and the contact surface thereof. Since stainless steel is used, corrosion occurs during plant operation.
錆等の発生を防止することができ、これによりプラント
運転初期の間隙を維持することができる。It is possible to prevent the occurrence of rust, etc., and thereby maintain the gap at the initial stage of plant operation.
(実施例) 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.
第1図(a)は本発明の一実施例の断面図、同図(b)
はその一部詳細断面図であり、これらの図に示すように
、炉水を駆動するポンプインペラ2は炉内に設置されて
おり、ポンプシャフト8を介してウェットモータ部10
と接続されている。ポンプシャフト8の大部分゛及びウ
ェットモータ部10はケーシング9の中に内蔵されてお
り、ケーシング9のケーシングネック部4は原子炉圧力
容器外壁下部のノズル部と溶接構造で結合されている。FIG. 1(a) is a sectional view of an embodiment of the present invention, and FIG. 1(b) is a sectional view of an embodiment of the present invention.
are partially detailed cross-sectional views, and as shown in these figures, a pump impeller 2 that drives reactor water is installed in the reactor, and is connected to a wet motor section 10 via a pump shaft 8.
is connected to. Most of the pump shaft 8 and the wet motor section 10 are housed in a casing 9, and the casing neck section 4 of the casing 9 is connected to a nozzle section at the lower part of the outer wall of the reactor pressure vessel by welding.
ざらに、上記係止部5及び係止部当り面6の部材をステ
ンレス鋼とし、このステンレス鋼はケーシング4あるい
は原子炉圧力容器外部スリーブ7の炭素鋼と溶接接合す
るものである。また係止部5及び係止部当り面6は、常
温で嵌め合い構造で接するように溶接俊表面仕上げを行
う。In general, the members of the locking portion 5 and the locking portion contact surface 6 are made of stainless steel, and this stainless steel is welded to the carbon steel of the casing 4 or the reactor pressure vessel outer sleeve 7. Further, the locking portion 5 and the locking portion abutment surface 6 are surface-finished by welding so that they fit into contact at room temperature.
次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.
常温では、係止部5と係止部当り面6は嵌め合い構造で
あるが、原子炉の通常運転時には内圧及び熱の影響を受
けて、両者の間に微小な間隙を生じている。そして、例
えば原子炉運転時に地震時に生じるような大きな横ゆれ
が発生すると、係止部5と係止部当り面6とが接触する
ことになるので、振動及び応力的に最も厳しい個所であ
るケーシング付は根部3の応力を低減させることができ
る。At room temperature, the locking portion 5 and the locking portion contact surface 6 have a fitting structure, but during normal operation of the nuclear reactor, a small gap is created between them due to the influence of internal pressure and heat. For example, if a large lateral vibration occurs during nuclear reactor operation, such as occurs during an earthquake, the locking part 5 and the locking part contact surface 6 will come into contact with each other, so the casing is the most severe part in terms of vibration and stress. The attachment can reduce the stress on the root portion 3.
ところで、この係止部の間隙と地震時にケーシング付は
根部に発生し得る最大応力の関係は、既に説明した第5
図に示すように、両者は路線形関係にある。By the way, the relationship between the gap of this locking part and the maximum stress that can occur in the root part of the case with a casing during an earthquake is explained in the fifth section already explained.
As shown in the figure, the two are in a line shape relationship.
そこで、上記係止部の間隙をできるだけ小さく保つこと
が重要となる。従来、提案されている係止部5及び係止
部当り面6は、第3図、第4図に示すようにケーシング
および原子炉圧力容器スリーブと同じ炭素鋼で形成され
ているためプラント運転中に腐食、錆等の発生が生じる
恐れかり、これらの影響を受けて係止部の初期間隙が徐
々に拡大してプラント寿命末期の間隙は初期間隙にくら
べ著しく大きくなる恐れがあった。Therefore, it is important to keep the gap between the locking portions as small as possible. Conventionally, the proposed locking portion 5 and locking portion contact surface 6 are made of the same carbon steel as the casing and the reactor pressure vessel sleeve, as shown in FIGS. Under the influence of these factors, the initial gap of the locking portion may gradually expand, and the gap at the end of the plant life may become significantly larger than the initial gap.
本実施例では、係止部5及び係止部当り面6にステンレ
ス鋼を用いることにより腐食、錆等の発生の恐れをなく
し、上記間隔がプラント運転初期間隙以上に拡大しない
構造としたものである。In this embodiment, stainless steel is used for the locking part 5 and the locking part contact surface 6 to eliminate the risk of corrosion, rust, etc., and the structure is such that the above-mentioned gap does not expand beyond the initial gap of plant operation. be.
第2図(a)は本発明の他の実施例の断面図、同図(b
)はその一部詳細断面図であり、これらの図に示すよう
に、係止部5をRPV外部スリーブ7側に、係止部当り
面6をケーシング4側に設けても上記実施例と同様な効
果を奏する。FIG. 2(a) is a sectional view of another embodiment of the present invention, and FIG. 2(b) is a sectional view of another embodiment of the present invention.
) is a partially detailed cross-sectional view of the same, and as shown in these figures, even if the locking part 5 is provided on the RPV outer sleeve 7 side and the locking part contact surface 6 is provided on the casing 4 side, the same result as in the above embodiment is obtained. It has a great effect.
[発明の効果]
以上述べたように、本発明によれば係止部間隙はプラン
ト寿命中、初期間隙が維持できるので、地震時にケーシ
ング付は根部に発生し得る最大応力も初期間隙の評価で
十分となり、本支持装置による耐B槻能及びその信頼性
が著しく向上させることができるという優れた効果を奏
する。[Effects of the Invention] As described above, according to the present invention, the initial gap can be maintained for the locking part gap during the life of the plant. This results in an excellent effect in that the present support device can significantly improve its ability to withstand B damage and its reliability.
第1図(a)及びは同図(b)は本発明の一実施例の断
面図及びその一部詳細断面図、第2図(a)及び同図(
b)は本発明の他の実施例の断面図及びその一部詳細断
面図、第3図及び第4図はいずれも従来のインターナル
ポンプの断面図、第5図は係止部間隙とケーシング付は
根部の地震時最大応力との関係を説明するための図であ
る。
1・・・原子炉圧力容器壁
2・・・ポンプインペア
3・・・ケーシング付は根
4・・・ケーシングネック部
5・・・係止部
6・・・係止部当り面
7・・・原子炉圧力容器外部スリーブ
8・・・ポンプシャフト
9・・・ケーシング
10・・・ウェットモータ
11・・・溶接部
代理人 弁理士 則 近 憲 佑
同 三俣弘文
°° 第1図
Ca)
第2図
第3図
第4図
同
↓
第5図FIGS. 1(a) and 1(b) are a sectional view and a partially detailed sectional view of one embodiment of the present invention, and FIGS. 2(a) and 2(b) are
b) is a sectional view of another embodiment of the present invention and a partially detailed sectional view thereof, FIGS. 3 and 4 are sectional views of a conventional internal pump, and FIG. 5 is a sectional view of a locking part gap and a casing. Attached is a diagram for explaining the relationship between the root and the maximum stress during an earthquake. 1... Reactor pressure vessel wall 2... Pump impair 3... Root with casing 4... Casing neck part 5... Locking part 6... Locking part contact surface 7...・Reactor pressure vessel external sleeve 8...Pump shaft 9...Casing 10...Wet motor 11...Welding department agent Patent attorney Noriyuki Ken Yudo Hirofumi Mitsumata °° Figure 1 Ca) 2 Figure 3 Figure 4 Same as Figure 5 ↓ Figure 5
Claims (1)
ブと前記原子炉圧力容器外壁下部に取付けられたポンプ
ケーシングとの間に間隙を有するように配置された原子
炉内蔵型ウェットモータポンプにおいて、前記ポンプケ
ーシングのネック部にステンレス鋼製の係止部をリング
状全周または数ケ所溶接するとともに前記係止部に対向
する前記スリーブの当り面にステンレス鋼を溶接したこ
とを特徴とする原子炉内蔵型ウェットモータポンプの耐
震支持装置。(1) In a reactor built-in wet motor pump arranged so that there is a gap between a sleeve extending downward from the lower part of the outer wall of the reactor pressure vessel and a pump casing attached to the lower part of the outer wall of the reactor pressure vessel, A nuclear reactor characterized in that a locking part made of stainless steel is welded to the neck part of the pump casing all around the ring shape or at several places, and stainless steel is welded to the abutting surface of the sleeve facing the locking part. Earthquake-resistant support device for built-in wet motor pump.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61159766A JPS6316295A (en) | 1986-07-09 | 1986-07-09 | Earthquakeproof supporter for nuclear reactor built-in type wet motor pump |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61159766A JPS6316295A (en) | 1986-07-09 | 1986-07-09 | Earthquakeproof supporter for nuclear reactor built-in type wet motor pump |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6316295A true JPS6316295A (en) | 1988-01-23 |
Family
ID=15700799
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61159766A Pending JPS6316295A (en) | 1986-07-09 | 1986-07-09 | Earthquakeproof supporter for nuclear reactor built-in type wet motor pump |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6316295A (en) |
-
1986
- 1986-07-09 JP JP61159766A patent/JPS6316295A/en active Pending
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