JPS644160B2 - - Google Patents

Info

Publication number
JPS644160B2
JPS644160B2 JP55125994A JP12599480A JPS644160B2 JP S644160 B2 JPS644160 B2 JP S644160B2 JP 55125994 A JP55125994 A JP 55125994A JP 12599480 A JP12599480 A JP 12599480A JP S644160 B2 JPS644160 B2 JP S644160B2
Authority
JP
Japan
Prior art keywords
water
pump
thermal barrier
casing
gap
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
Application number
JP55125994A
Other languages
Japanese (ja)
Other versions
JPS5750692A (en
Inventor
Masao Niwano
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
Tokyo Shibaura Electric Co Ltd
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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP55125994A priority Critical patent/JPS5750692A/en
Publication of JPS5750692A publication Critical patent/JPS5750692A/en
Publication of JPS644160B2 publication Critical patent/JPS644160B2/ja
Granted 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
    • 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

  • Structures Of Non-Positive Displacement Pumps (AREA)

Description

【発明の詳細な説明】 本発明は原子炉再循環ポンプのメカニカルシー
ルに注入している冷水がポンプ軸に沿つて流れ、
羽根車上部付近で高温の炉水と混合するために発
生する軸の熱応力を軽減するための熱障壁を有す
る再循環ポンプに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention is characterized in that cold water injected into a mechanical seal of a nuclear reactor recirculation pump flows along the pump shaft.
The present invention relates to a recirculation pump having a thermal barrier to reduce shaft thermal stress caused by mixing with high temperature reactor water near the top of the impeller.

沸騰水型原子炉で用いられている一次冷却材循
環のための原子炉再循環ポンプでは軸シールとし
てメカニカルシールを有している。このメカニカ
ルシールは度々交換が必要であり、交換作業時の
被曝量を低減し、さらにメカニカルシール部に異
物が混入し、シールの寿命が短縮するのを防止す
るために外部より清浄な冷水を注入している。こ
の注入水(メカニカルシールパージ水)の一部は
複数のシール室の各室の圧力を調整するために外
部に流出するが、一部はポンプ軸に沿つてケーシ
ング内に流れ込む。
Reactor recirculation pumps for primary coolant circulation used in boiling water reactors have mechanical seals as shaft seals. This mechanical seal needs to be replaced frequently, and clean cold water is injected from the outside in order to reduce the amount of radiation exposure during replacement work and to prevent foreign matter from getting into the mechanical seal and shortening the seal's lifespan. are doing. A portion of this injection water (mechanical seal purge water) flows out to the outside to adjust the pressure in each of the plurality of seal chambers, but a portion flows into the casing along the pump shaft.

ケーシング内に流れ込んだパージ水の一部はポ
ンプ羽根車上部のポンプ軸周囲において高温の炉
水と混合する。シール室内の水温は約30〜50℃、
炉水は約270〜280℃であるため両者が混合する付
近では温度の変動が生じ、その結果ポンプ軸表面
およびそれと相対するポンプケーシングカバー内
表面には熱応力が発生し、温度変動巾と変動周期
如何によつてはポンプ軸表面およびケーシングカ
バー内表面にクラツクの発生する恐れがある。
A portion of the purge water that has flowed into the casing mixes with high-temperature reactor water around the pump shaft above the pump impeller. The water temperature in the sealing chamber is approximately 30-50℃.
Since reactor water is approximately 270 to 280°C, temperature fluctuations occur near the mixing of the two, resulting in thermal stress on the pump shaft surface and the inner surface of the pump casing cover that faces it, causing temperature fluctuations and fluctuations. Depending on the cycle, cracks may occur on the pump shaft surface and the inner surface of the casing cover.

本発明は、上記問題点に対してなされたもの
で、ポンプ軸表面およびケーシングカバー表面付
近で低温パージ水と高温炉水との混合をなくし、
熱応力によるクラツク発生を防止できる原子炉再
循環ポンプを提供することを目的としている。
The present invention has been made to solve the above problems, and eliminates mixing of low temperature purge water and high temperature reactor water near the pump shaft surface and casing cover surface.
The purpose of the present invention is to provide a nuclear reactor recirculation pump that can prevent cracks from occurring due to thermal stress.

以下、実施例の図面を参照して本発明について
説明する。第1図は原子炉再循環ポンプの断面図
である。ポンプ中心のポンプ軸1には羽根車2が
固定される。羽根車2の外周には流路を形成して
ケーシング3が設置され、ケーシング3の上部に
はケーシングカバー4が固定される。このケーシ
ングカバー4と前記ポンプ軸1とは間隙5を有
し、さらにメカニカルシール6が配置される。前
記ケーシング3とポンプ軸1間には円筒形状した
ポンプベアリング5が設けられる。このポンプベ
アリング5はケーシングカバー4に固定され、円
筒の軸のほぼ中間位置には、半径方向に複数個の
孔7が穿設される。また、このポンプベアリング
5の内部にはポンプベアリング5と同心円上に円
筒部材であるジヤーナル8が配置される。このジ
ヤーナル8は前記羽根車2の一部を形成するもの
である。さらに、ジヤーナル8の内部であつてジ
ヤーナル8と同心円上には、ケーシングカバー4
に取りつけられる円筒形状の熱障壁10が設けら
れる。
The present invention will be described below with reference to drawings of embodiments. FIG. 1 is a cross-sectional view of a nuclear reactor recirculation pump. An impeller 2 is fixed to a pump shaft 1 at the center of the pump. A casing 3 is installed on the outer periphery of the impeller 2 to form a flow path, and a casing cover 4 is fixed to the upper part of the casing 3. This casing cover 4 and the pump shaft 1 have a gap 5, and a mechanical seal 6 is further arranged. A cylindrical pump bearing 5 is provided between the casing 3 and the pump shaft 1. The pump bearing 5 is fixed to the casing cover 4, and a plurality of holes 7 are bored in the radial direction approximately in the middle of the cylindrical axis. Further, inside the pump bearing 5, a journal 8, which is a cylindrical member, is arranged concentrically with the pump bearing 5. This journal 8 forms a part of the impeller 2. Furthermore, inside the journal 8 and concentrically with the journal 8, a casing cover 4 is provided.
A cylindrical thermal barrier 10 is provided which is attached to the.

尚、循環水吸込部9と熱障壁10の下部間隙1
1とを連通する孔12が羽根車2に複数個穿設さ
れ。前記熱障壁10の内外部には間隙13,14
が形成される。また、ケーシングカバー4は支持
台15により挾持されて支持される。前記羽根車
2の下端部近傍でケーシング3の吸込部にはウエ
アリング16が設置される。メカニカルシール6
の下部にはシール室17が設置される。
In addition, the lower gap 1 between the circulating water suction part 9 and the thermal barrier 10
A plurality of holes 12 are bored in the impeller 2 to communicate with the impeller 2. Gaps 13 and 14 are provided inside and outside the thermal barrier 10.
is formed. Further, the casing cover 4 is held and supported by a support stand 15. A wear ring 16 is installed in the suction portion of the casing 3 near the lower end of the impeller 2 . Mechanical seal 6
A seal chamber 17 is installed in the lower part of.

次に作用について説明する。 Next, the effect will be explained.

原子炉再循環ポンプのシール室17に注入され
たパージ水18はポンプ軸1とケーシングカバー
2の間隙5を通つて羽根車2の上方にあるポンプ
軸1と熱障壁10の間隙13に入る。羽根車2に
より昇圧された炉水19はポンプベアリング5と
ケーシング3の間隙20からポンプベアリング5
とジヤーナル8の間隙21を通り、ジヤーナル8
と熱障壁10の間隙14に入る。一方間隙13に
流入した冷温のパージ水18は熱障壁10の下方
領域1に至るまでにポンプ軸1および熱障壁10
からの熱流入により暖められ領域11で炉水19
と混合し羽根車2に設けられた流路12を通つて
羽根車2の吸込部9に流れる。
Purge water 18 injected into the seal chamber 17 of the reactor recirculation pump passes through the gap 5 between the pump shaft 1 and the casing cover 2 and enters the gap 13 between the pump shaft 1 and the thermal barrier 10 above the impeller 2 . Reactor water 19 pressurized by the impeller 2 flows from the pump bearing 5 through the gap 20 between the pump bearing 5 and the casing 3.
through the gap 21 between journal 8 and journal 8.
and enters the gap 14 of the thermal barrier 10. On the other hand, the cold purge water 18 flowing into the gap 13 reaches the pump shaft 1 and the thermal barrier 10 by the time it reaches the lower region 1 of the thermal barrier 10.
Reactor water 19 is heated in region 11 by heat inflow from
It flows into the suction part 9 of the impeller 2 through the flow path 12 provided in the impeller 2.

熱障壁10はケーシングカバー4に取付けら
れ、パージ水18と炉水19は熱障壁10を介し
て熱交換を行なうため熱障壁10の下方領域11
でパージ水18と炉水19が混合する際の温度変
動は小さくなる。さらにパージ水18と炉水19
の混合がポンプ軸1およびケーシングカバー4の
内表面から離れた位置で行なわれるためポンプ軸
1の外表面とケーシングカバー4の内表面におけ
る熱応力の問題はなくなる。
The thermal barrier 10 is attached to the casing cover 4 , and the lower area 11 of the thermal barrier 10 is attached to the casing cover 4 so that the purge water 18 and the reactor water 19 exchange heat through the thermal barrier 10 .
In this case, the temperature fluctuation when the purge water 18 and the reactor water 19 are mixed becomes small. Furthermore, purge water 18 and reactor water 19
Since the mixing is performed at a position away from the inner surface of the pump shaft 1 and the casing cover 4, the problem of thermal stress on the outer surface of the pump shaft 1 and the inner surface of the casing cover 4 is eliminated.

第2図は熱障壁10aをポンプ軸1に取り付け
た場合でありパージ水18と炉水19は熱障壁1
0aとジヤーナル8の間隙14aで混合する。熱
障壁10aはポンプ軸1とともに回転するため間
隙14aに流入したパージ水18は十分に撹拌さ
れ、炉水19との混合が速やかに行なわれる。
Figure 2 shows the case where the thermal barrier 10a is attached to the pump shaft 1, and the purge water 18 and reactor water 19 are connected to the thermal barrier 1.
0a and the gap 14a between the journal 8. Since the thermal barrier 10a rotates together with the pump shaft 1, the purge water 18 flowing into the gap 14a is sufficiently stirred and mixed with the reactor water 19 quickly.

第3図は熱障壁10をケーシングカバー4に、
熱障壁10aをポンプ軸1に取付けた場合であり
パージ水18は熱障壁10,10aの間隙13b
に、炉水19は熱障壁10とジヤーナル8の間隙
14bに流れ込む。この場合パージ水18は間隙
13b内で暖められ、炉水19は間隙14b内で
冷やされる。またパージ水18と炉水19の流路
が別々になり、パージ水18と炉水19の混合は
熱障壁10,10aの下方領域で行なわれるため
ポンプ軸1の外表面、ケーシングカバーの内表面
およびジヤーナル8の表面での熱応力の問題はな
くなる。
FIG. 3 shows the heat barrier 10 attached to the casing cover 4,
This is a case where the thermal barrier 10a is attached to the pump shaft 1, and the purge water 18 is in the gap 13b between the thermal barriers 10 and 10a.
Then, the reactor water 19 flows into the gap 14b between the thermal barrier 10 and the journal 8. In this case, purge water 18 is warmed within gap 13b, and reactor water 19 is cooled within gap 14b. In addition, the flow paths for purge water 18 and reactor water 19 are separated, and mixing of purge water 18 and reactor water 19 is performed in the area below the thermal barriers 10 and 10a, so the outer surface of the pump shaft 1 and the inner surface of the casing cover And the problem of thermal stress on the surface of the journal 8 is eliminated.

本発明による熱障壁の形状については一般的に
は円筒状のものが考えられるが、熱交換効率を高
めるため、表面形状を波形にしたり、流れに乱れ
を与えるため凸凹や突起をもつ形状にすることが
より効果的となる。
The shape of the thermal barrier according to the present invention is generally considered to be cylindrical, but in order to increase heat exchange efficiency, the surface shape may be waveform, or it may have a shape with unevenness or protrusions to create turbulence in the flow. becomes more effective.

第4図はパージ水18と炉水19の熱交換量を
増やすために熱障壁の形状を変える場合の例であ
る。パージ水18と炉水19は熱障壁間の十分な
る間隙13cにより熱交換を行なう。
FIG. 4 shows an example of changing the shape of the thermal barrier in order to increase the amount of heat exchange between the purge water 18 and the reactor water 19. Purge water 18 and reactor water 19 exchange heat through a sufficient gap 13c between the thermal barriers.

第5図は熱障壁10bの表面を波形にした例で
あり、パージ水18と炉水19に乱れを与え、熱
交換効率を高めることができる。
FIG. 5 shows an example in which the surface of the thermal barrier 10b is corrugated, which gives turbulence to the purge water 18 and the reactor water 19, thereby increasing the heat exchange efficiency.

第6図はパージ水18と炉水19の混合をより
効果的に行なうため熱障壁10cに孔22を設け
た例である。間隙13内のパージ水18は遠心力
により孔22から間隙14に噴出され炉水19と
混合する。
FIG. 6 shows an example in which holes 22 are provided in the thermal barrier 10c in order to more effectively mix the purge water 18 and the reactor water 19. Purge water 18 in gap 13 is jetted out from hole 22 into gap 14 by centrifugal force and mixes with reactor water 19.

以上説明したように本発明によれば低温のパー
ジ水と高温の炉水が直接、かつポンプ軸およびケ
ーシングカバー表面付近で混合することがなくな
るので熱応力によるクラツク発生を防止できる。
As explained above, according to the present invention, low-temperature purge water and high-temperature reactor water do not mix directly and near the pump shaft and casing cover surface, so it is possible to prevent cracks from occurring due to thermal stress.

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

第1図は本発明の一実施例による原子炉再循環
ポンプの断面図、第2図から第6図は第1図の熱
障壁の他の実施例を示す状態図である。 1……ポンプ軸、2……羽根車、3……ケーシ
ング、4……ケーシングカバー、5……ポンプベ
アリング、6……メカニカルシール、8……ジヤ
ーナル、10……熱障壁。
FIG. 1 is a cross-sectional view of a nuclear reactor recirculation pump according to one embodiment of the present invention, and FIGS. 2 to 6 are state diagrams showing other embodiments of the thermal barrier of FIG. 1... Pump shaft, 2... Impeller, 3... Casing, 4... Casing cover, 5... Pump bearing, 6... Mechanical seal, 8... Journal, 10... Thermal barrier.

Claims (1)

【特許請求の範囲】[Claims] 1 ポンプ軸端部に固定される羽根車と、循環水
の流路を形成するケーシングと、このケーシング
に固定されるケーシングカバーと、このケーシン
グカバーと前記ポンプ軸間に設置されるメカニカ
ルシールと、前記ケーシングカバーに取り付けら
れるポンプベアリングと、このポンプベアリング
と間隙を介して前記羽根車に形成されるジヤーナ
ルと、このジヤーナル内部に設けられる熱障壁と
からなる原子炉再循環ポンプ。
1. An impeller fixed to the end of the pump shaft, a casing forming a circulating water flow path, a casing cover fixed to the casing, and a mechanical seal installed between the casing cover and the pump shaft, A nuclear reactor recirculation pump comprising a pump bearing attached to the casing cover, a journal formed in the impeller through a gap from the pump bearing, and a thermal barrier provided inside the journal.
JP55125994A 1980-09-12 1980-09-12 Nuclear reactor circulation pump Granted JPS5750692A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55125994A JPS5750692A (en) 1980-09-12 1980-09-12 Nuclear reactor circulation pump

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55125994A JPS5750692A (en) 1980-09-12 1980-09-12 Nuclear reactor circulation pump

Publications (2)

Publication Number Publication Date
JPS5750692A JPS5750692A (en) 1982-03-25
JPS644160B2 true JPS644160B2 (en) 1989-01-24

Family

ID=14924082

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55125994A Granted JPS5750692A (en) 1980-09-12 1980-09-12 Nuclear reactor circulation pump

Country Status (1)

Country Link
JP (1) JPS5750692A (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60168582U (en) * 1984-04-13 1985-11-08 エムケ−精工株式会社 cleaning equipment
JPH0319980Y2 (en) * 1985-04-10 1991-04-26
JPS62251261A (en) * 1986-04-23 1987-11-02 Tokyo Tatsuno Co Ltd Spray type car washing machine
JPH0664183B2 (en) * 1990-10-26 1994-08-22 株式会社荏原製作所 High temperature pump thermal fatigue prevention device
KR100407700B1 (en) * 2001-10-04 2003-12-01 한국수력원자력 주식회사 Primary coolant inflow reducing device for Main Coolant Pump

Also Published As

Publication number Publication date
JPS5750692A (en) 1982-03-25

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