JP2811682B2 - Main steam nozzle of reactor pressure vessel - Google Patents
Main steam nozzle of reactor pressure vesselInfo
- Publication number
- JP2811682B2 JP2811682B2 JP63238104A JP23810488A JP2811682B2 JP 2811682 B2 JP2811682 B2 JP 2811682B2 JP 63238104 A JP63238104 A JP 63238104A JP 23810488 A JP23810488 A JP 23810488A JP 2811682 B2 JP2811682 B2 JP 2811682B2
- Authority
- JP
- Japan
- Prior art keywords
- nozzle
- main steam
- pressure vessel
- reactor pressure
- pipe
- 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 - Fee Related
Links
- 238000001514 detection method Methods 0.000 claims description 11
- 239000011148 porous material Substances 0.000 claims description 9
- 230000000149 penetrating effect Effects 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 230000002787 reinforcement Effects 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 230000008719 thickening Effects 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 239000007921 spray Substances 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 1
- 230000001629 suppression 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】 「産業上の利用分野」 本発明は、原子炉圧力容器の主蒸気ノズルに係り、特
に、沸騰水型原子炉の発生蒸気を主蒸気系配管に送り出
すノズルの部分に、ベンチュリー管の機能及び流量制限
機能を付与する技術に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a main steam nozzle of a reactor pressure vessel, and more particularly to a nozzle portion for sending steam generated from a boiling water reactor to a main steam system pipe. The present invention relates to a technology for providing a function of a venturi tube and a flow rate limiting function.
「従来の技術」 従来、沸騰水型原子炉における原子炉圧力容器の周囲
には、主蒸気系だけではなく、給水系、高圧スプレイ
系、低圧スプレイ系、低圧注水系等の各種系統の配管が
多数配設される。Conventional technology Conventionally, in the boiling water reactor, around the reactor pressure vessel, pipes of various systems such as water supply system, high pressure spray system, low pressure spray system, and low pressure water injection system as well as the main steam system were installed. Many are arranged.
そのため、原子炉圧力容器の周辺、つまり、原子炉格
納容器の内部における各種系統の配管の経路、あるいは
単純化を図ることが要求される。Therefore, it is required to simplify or simplify the piping of various systems around the reactor pressure vessel, that is, inside the containment vessel.
第３図は、沸騰水型原子炉における原子炉格納容器の
従来例を示すもので、コンクリート製生体遮蔽壁（原子
炉建屋壁）１に囲まれた鋼製容器２の中に、原子炉圧力
容器３、原子炉ペデスタル４、原子炉遮蔽壁５がそれぞ
れ収納されるとともに、ダイヤフラムフロア６によっ
て、ドライウエル７とサプレッションチェンバ８とを区
画するようにしている。FIG. 3 shows a conventional example of a reactor containment vessel in a boiling water reactor, in which a reactor pressure is placed in a steel vessel 2 surrounded by a concrete living shielding wall (reactor building wall) 1. The container 3, the reactor pedestal 4, and the reactor shield wall 5 are respectively housed, and the dry well 7 and the suppression chamber 8 are partitioned by the diaphragm floor 6.
そして、原子炉圧力容器３と主蒸気系配管９との接続
部分には、第４図に示すようなノズル構造が採用され、
該ノズル10は、交差斜線で示す補強用肉厚部Ａを有し
て、その近傍において付与される熱及び機械的応力に対
して十分な強度を保持するように配慮されている。A nozzle structure as shown in FIG. 4 is employed in a connection portion between the reactor pressure vessel 3 and the main steam system pipe 9,
The nozzle 10 has a thick wall portion A for reinforcement indicated by oblique lines and is designed to maintain sufficient strength against heat and mechanical stress applied in the vicinity thereof.
また、主蒸気系配管９では、その配管経路における破
断事故時の最大蒸気量を制限することと、蒸気流量を検
出することとを目的として、第５図に示すような流量制
限器11を前記ドライウエル７の適宜位置に設置すること
が考慮されている。該流量制限器11は、ラッパ管（ベン
チュリー管）状の絞り管12と、この絞り管12の内部と主
蒸気系配管９の外部とを連通させる細孔13と、絞り管12
の入口側に位置して滑らかに流路断面を絞る絞り部12a
及び出口側に位置して徐々に流路を広げるテーパ部12b
とを具備する構成である。In the main steam system pipe 9, a flow restrictor 11 as shown in FIG. 5 is provided for the purpose of limiting the maximum steam amount at the time of a breakage accident in the pipe path and detecting the steam flow rate. It is considered that the dry well 7 is installed at an appropriate position. The flow restrictor 11 comprises a throttle pipe 12 in the form of a trumpet pipe (Venturi pipe), a pore 13 for communicating the inside of the throttle pipe 12 with the outside of the main steam system pipe 9, and a throttle pipe 12.
Throttle section 12a located on the inlet side of
And the tapered part 12b located on the outlet side to gradually widen the flow path
It is a configuration provided with:
そして、流量制限器11の下流位置で主蒸気系配管９の
一部が破断する事故が生じた場合にあっても、破断の想
定箇所からの漏洩流量の最大値が通常流量の２倍程度に
抑制されるように、絞り管12の各部寸法が選定されるも
のであり、また、前記細孔13を利用して、流路の前後の
差圧を測定することによって、流量の検出が行なわれ
る。Then, even if an accident occurs in which a part of the main steam system pipe 9 breaks at a position downstream of the flow restrictor 11, the maximum value of the leakage flow rate from the supposed point of the breakage becomes about twice the normal flow rate. The size of each part of the throttle pipe 12 is selected so as to be suppressed, and the flow rate is detected by measuring the differential pressure across the flow path using the pores 13. .
「発明が解決しようとする課題」 しかしながら、主蒸気系配管９の途中に流量制限器11
を介在させる構造であると、流量制限器11を取り付ける
ために、主蒸気系配管９の部分に適当な長さの直線部の
設定が必要となり、検出用機器の接続用スペースの確保
と相まって、配管の引き回しの自由度が損なわれ易く、
また、流量制限器11は、主蒸気系配管９の内部に溶接に
よって固定されることになるが、その溶接部の信頼性の
確保が要求されることになる。“Problem to be Solved by the Invention” However, the flow restrictor 11
In order to mount the flow restrictor 11, it is necessary to set a linear portion of an appropriate length in the main steam system piping 9 and to secure a space for connecting the detection device, The degree of freedom of piping is easily lost,
Further, the flow restrictor 11 is fixed inside the main steam system pipe 9 by welding, but it is required to ensure the reliability of the welded portion.
本発明は、このような従来技術の課題を有効に解決す
るものであり、加えて、主蒸気系配管の内部に溶接によ
って他の部材を取り付けることを省略し、主蒸気系配管
の全域での流量制限を行なうことを目的とするものであ
る。The present invention effectively solves such problems of the prior art. In addition, the present invention omits attaching other members to the inside of the main steam system piping by welding, and can reduce the entire area of the main steam system piping. The purpose is to limit the flow rate.
「課題を解決するための手段」 原子炉圧力容器と主蒸気系配管とを接続するために外
方に向けて突設されるノズルにおいて、該ノズルの管壁
内面にベンチュリー管機能を有する内面形状設定用肉厚
部を配設してなり、原子炉圧力容器に配される絞り部と
内面形状設定用肉厚部の外方よりに配されるテーパ部と
の間に、ノズルの最少内径をなす円筒穴状の直線部を介
在状態にするとともに、該直線部における外方よりに、
ノズルを半径方向に貫通する細孔と、該細孔に接続され
て圧力検出を行なうための圧力検出孔とを配した構成を
採用している。[Means for Solving the Problems] In a nozzle protruding outward to connect a reactor pressure vessel and a main steam system pipe, an inner surface shape having a Venturi pipe function is provided on an inner surface of a pipe wall of the nozzle. A thick portion for setting is provided, and a minimum inner diameter of the nozzle is provided between a constricted portion provided in the reactor pressure vessel and a tapered portion provided from the outside of the thick portion for setting the inner surface. While making the cylindrical hole-shaped linear part to be interposed, from the outside of the linear part,
A configuration is used in which a fine hole penetrating through the nozzle in the radial direction and a pressure detection hole connected to the fine hole for performing pressure detection are arranged.
「作用」 ノズル部分の各種強度は、管壁内部における内面形状
設定用肉厚部と、外表面に必要に応じて付けられる内面
形状設定用肉厚部によって得られる。したがって、主蒸
気系配管の途中には、流路と交差する他の部材の取り付
けを必要としない。[Operation] Various strengths of the nozzle portion are obtained by the inner surface shape setting thick portion inside the tube wall and the inner surface shape setting thick portion attached to the outer surface as necessary. Therefore, it is not necessary to attach another member that intersects the flow path in the middle of the main steam system pipe.
そして、主蒸気がノズルを通過する場合に、ベンチュ
リー管の機能を有する内面形状設定用肉厚部によって絞
られることにより、ノズルの下流部分が主蒸気系の全域
部分になり、破断する事故が生じた場合にあって、その
漏洩流量を制限する。また、ノズル部分における細孔及
び圧力検出孔が、原子炉圧力容器に近接して配されるた
めに、例えば原子炉圧力容器の内部圧力と圧力検出孔を
介して検出される圧力とで差圧を求めるにより、流量の
検出が行なわれる。Then, when the main steam passes through the nozzle, it is narrowed down by the inner surface shape setting thick portion having the function of the Venturi tube, so that the downstream portion of the nozzle becomes the entire region of the main steam system, causing an accident of breaking. In that case, limit the leakage flow rate. Further, since the pores and the pressure detection holes in the nozzle portion are arranged close to the reactor pressure vessel, for example, the pressure difference between the internal pressure of the reactor pressure vessel and the pressure detected via the pressure detection holes is reduced. , The flow rate is detected.
「実施例」 以下、本発明に係る原子炉圧力容器の主蒸気ノズルの
一実施例を第１図及び第２図に基づいて説明する。Embodiment An embodiment of the main steam nozzle of the reactor pressure vessel according to the present invention will be described below with reference to FIGS. 1 and 2.
該一実施例における主蒸気ノズル10は、その管壁の内
外面の縦断面形状が第１図及び第２図に示すように設定
されて、管穴の部分にベンチュリー管の機能が付与され
ているとともに、交差斜線で示す内外２つの肉厚部Ｂ・
Ｃによる補強がなされている。In the main steam nozzle 10 in the embodiment, the vertical cross-sectional shape of the inner and outer surfaces of the pipe wall is set as shown in FIGS. 1 and 2, and the function of the Venturi pipe is given to the pipe hole portion. And the inner and outer thick portions B
C has been reinforced.
即ち、従来例で説明した補強用肉厚部Ａに代えて、そ
の一部を減肉した状態の外面形状設定用肉厚部Ｂと、補
強を兼用するとともに、ベンチュリー機能及び流量制限
機能を持たせるための絞り部12aの形状に相当する内面
形状設定用肉厚部Ｃとによって構成される。That is, in place of the thickening portion A for reinforcement described in the conventional example, the thickening portion B for setting the outer surface in a state where a part of the thickening portion is reduced, and also serves as reinforcement, and has a venturi function and a flow rate limiting function. And an inner surface shape setting thick portion C corresponding to the shape of the constricted portion 12a.
また、図示例では、絞り部12aとテーパ部12bとの間
に、直線部12cが介在させられているとともに、該直線
部12cの管壁に半径方向に沿う細孔13が明けられて、該
細孔13と斜めに交差する圧力検出孔14が連通状態に明け
られており、各部の寸法、つまり、内径d1〜d3、角度θ
３〜θ４、長さL1〜L3、曲率ｒ等は、第２図に示す例の
ように設定される。Further, in the illustrated example, a linear portion 12c is interposed between the narrowed portion 12a and the tapered portion 12b, and a pore 13 is formed along a radial direction in a tube wall of the linear portion 12c, and the linear portion 12c is formed. A pressure detection hole 14 obliquely intersecting with the pore 13 is opened in a communicating state, and the dimensions of each part, that is, the inner diameter d 1 to d 3 , the angle θ
3 to θ 4 , lengths L 1 to L 3 , curvature r, and the like are set as in the example shown in FIG.
したがって、主蒸気ノズル10における最少内径d1は、
主蒸気系配管９の内径d3の約0.55倍に相当する。このた
め、ノズル部分における強度は、２つの肉厚部Ｂ・Ｃに
よって設定されるとともに、ノズル直径が全体的に小さ
くなるために、強度上の有利性が生じる。Therefore, minimum inner diameter d 1 in the main steam nozzle 10,
Corresponds to about 0.55 times the inside diameter d 3 of the main steam piping 9. For this reason, the strength at the nozzle portion is set by the two thick portions B and C, and the nozzle diameter is reduced as a whole.
一方、主蒸気がノズル部分を通過する際の直線部12c
の圧力を、細孔13と圧力検出孔14とを介して検出すると
ともに、その検出圧力と、例えばノズル10が設けられて
いる原子炉圧力容器３の内部圧力とを比較して、これら
の差圧を求めるにより、主蒸気流量の測定を行なうこと
ができる。On the other hand, the straight portion 12c when the main steam passes through the nozzle
Is detected through the pores 13 and the pressure detection holes 14, and the detected pressure is compared with, for example, the internal pressure of the reactor pressure vessel 3 provided with the nozzle 10. By determining the pressure, a measurement of the main steam flow can be made.
また、主蒸気系において、配管破断事故が生じた場合
を考慮すると、流量制限機能がノズル部分に付与されて
いるために、ノズル部分よりも下流、言い替えると主蒸
気系の全域の流量制限を行なうことができることにな
る。In addition, in consideration of the case where a pipe breakage accident occurs in the main steam system, since the flow rate limiting function is provided to the nozzle portion, the flow rate is limited downstream of the nozzle portion, in other words, the entire region of the main steam system. You can do it.
「発明の効果」 以上説明したように本発明に係る原子炉圧力容器の主
蒸気ノズルは、 ノズルの穴の部分にベンチュリー管の機能が付与され
るものであるから、その下流になる主蒸気系の全域を対
象とした流量制限機能を具備するものとし、従来例より
も保護範囲を拡大することができる。[Effects of the Invention] As described above, the main steam nozzle of the reactor pressure vessel according to the present invention is provided with the function of the Venturi tube in the hole of the nozzle. Is provided with a flow rate limiting function for the entire region, and the protection range can be expanded as compared with the conventional example.
従来例と比較して、主蒸気系配管の途中に溶接等によ
る他の部材の取り付けを必要とせず、構造の単純化を図
ることができる。Compared with the conventional example, it is not necessary to attach other members by welding or the like in the middle of the main steam system pipe, and the structure can be simplified.
ノズル部分に内面形状設定用肉厚部を形成しているた
め、従来例と比較して直径を小さくし、高度向上の点で
有利となる。Since the thick portion for setting the inner surface is formed in the nozzle portion, the diameter is reduced as compared with the conventional example, which is advantageous in improving the altitude.
絞り部とテーパ部との間に、最少内径をなす直線部が
介在して、この部分で主蒸気が直線的に導かれるととも
に、直線部における外方よりの細孔及び圧力検出孔によ
り圧力の検出がなされるため、主蒸気の流れが安定して
正確な圧力の検出を行なうことができる。Between the constricted portion and the tapered portion, a linear portion having the minimum inner diameter is interposed, and the main steam is linearly guided in this portion, and the pressure is detected by the outside pores and the pressure detecting holes in the linear portion. Since the detection is performed, the flow of the main steam is stabilized, and accurate pressure detection can be performed.
等の優れた効果を奏するものである。And so on.
【図面の簡単な説明】 第１図及び第２図は本発明に係る原子炉圧力容器の主蒸
気ノズルの一実施例を示すもので、第１図は縦断面図、
第２図はノズル各部の寸法例を記載したモデル図、第３
図は原子炉格納容器の従来例を示す正断面図、第４図は
第３図の鎖線IV部分の拡大図、第５図は第３図の鎖線Ｖ
部分の拡大である。 ２……鋼製容器、 ３……原子炉圧力容器、 ７……ドライウエル、 ９……主蒸気系配管、 10……ノズル、 11……流量制限器、 12……絞り管、 12a……絞り部、 12b……テーパ部、 12c……直線部、 13……細孔、 14……圧力検出孔、 Ａ……補強用肉厚部、 Ｂ……外面形状設定用肉厚部、 Ｃ……内面形状設定用肉厚部。BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 and FIG. 2 show one embodiment of a main steam nozzle of a reactor pressure vessel according to the present invention, FIG.
FIG. 2 is a model diagram showing an example of dimensions of each part of the nozzle, and FIG.
FIG. 4 is a front sectional view showing a conventional example of a reactor containment vessel, FIG. 4 is an enlarged view of a portion indicated by a chain line IV in FIG. 3, and FIG. 5 is a chain line V in FIG.
It is an enlargement of a part. 2 ... steel vessel, 3 ... reactor pressure vessel, 7 ... dry well, 9 ... main steam system piping, 10 ... nozzle, 11 ... flow restrictor, 12 ... throttle pipe, 12a ... Restricted portion, 12b ... taper portion, 12c ... linear portion, 13 ... pore, 14 ... pressure detection hole, A ... thick portion for reinforcement, B ... thick portion for external surface shape setting, C ... ... Thick part for setting the inner surface shape.
Claims (1)
（９）とを接続するために外方に向けて突設されるノズ
ル（10）において、該ノズルの管壁内面にベンチュリー
管機能を有する内面形状設定用肉厚部（Ｃ）を配設して
なり、原子炉圧力容器に配される絞り部（12a）と内面
形状設定用肉厚部の外方よりに配されるテーパ部（12
b）との間に、ノズルの最少内径をなす円筒穴状の直線
部（12c）を介在状態に形成するとともに、該直線部に
おける外方よりに、ノズルを半径方向に貫通する細孔
（13）と、該細孔に接続されて圧力検出を行なうための
圧力検出孔（14）とを配した原子炉圧力容器の主蒸気ノ
ズル。A nozzle (10) protruding outwardly for connecting a reactor pressure vessel (3) and a main steam system pipe (9) to a venturi pipe on an inner surface of a pipe wall of the nozzle. A thick part (C) for internal surface shape setting having a function is provided, and a tapered part (12a) arranged on the reactor pressure vessel and a taper arranged from the outside of the thick part for internal surface shape setting Department (12
b), a cylindrical hole-shaped linear portion (12c) having the minimum inner diameter of the nozzle is formed in an intervening state, and a fine hole (13) radially penetrating the nozzle from the outside of the linear portion. ) And a pressure detection hole (14) connected to the pore for detecting pressure. The main steam nozzle of the reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63238104A JP2811682B2 (en) | 1988-09-22 | 1988-09-22 | Main steam nozzle of reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63238104A JP2811682B2 (en) | 1988-09-22 | 1988-09-22 | Main steam nozzle of reactor pressure vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0287096A JPH0287096A (en) | 1990-03-27 |
| JP2811682B2 true JP2811682B2 (en) | 1998-10-15 |
Family
ID=17025237
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63238104A Expired - Fee Related JP2811682B2 (en) | 1988-09-22 | 1988-09-22 | Main steam nozzle of reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2811682B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2019168572A3 (en) * | 2017-12-18 | 2019-11-07 | GE - Hitachi Nuclear Energy Americas LLC | Multiple-path flow restrictor nozzle |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102345737A (en) * | 2010-07-28 | 2012-02-08 | 清华大学 | Nozzle of pressure vessel |
| WO2020252434A1 (en) * | 2019-06-14 | 2020-12-17 | Ge-Hitachi Nuclear Energy Americas | Integral pressure vessel penetrations and systems and methods for using and fabricating the same |
| JP7725424B2 (en) * | 2022-06-01 | 2025-08-19 | 日立Ｇｅベルノバニュークリアエナジー株式会社 | nuclear power plant |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3981833A (en) * | 1975-04-01 | 1976-09-21 | Standard Oil Company (Indiana) | Starch/polyester resin composition |
-
1988
- 1988-09-22 JP JP63238104A patent/JP2811682B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2019168572A3 (en) * | 2017-12-18 | 2019-11-07 | GE - Hitachi Nuclear Energy Americas LLC | Multiple-path flow restrictor nozzle |
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| Publication number | Publication date |
|---|---|
| JPH0287096A (en) | 1990-03-27 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |