JP2000137091A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- JP2000137091A JP2000137091A JP10312270A JP31227098A JP2000137091A JP 2000137091 A JP2000137091 A JP 2000137091A JP 10312270 A JP10312270 A JP 10312270A JP 31227098 A JP31227098 A JP 31227098A JP 2000137091 A JP2000137091 A JP 2000137091A
- Authority
- JP
- Japan
- Prior art keywords
- cooling water
- core tank
- injection nozzle
- reactor
- emergency cooling
- 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.)
- Withdrawn
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【発明の属する技術分野】本発明は、原子炉容器内に設
けられた炉心槽の外壁面に向けて非常用冷却水を噴出す
る非常用冷却水注入ノズルを備えた加圧水型原子炉等の
原子炉に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor such as a pressurized water reactor having an emergency cooling water injection nozzle for jetting emergency cooling water toward an outer wall surface of a core vessel provided in a reactor vessel. About the furnace.
【0002】[0002]
【従来の技術】従来、この種の原子炉は図3に示すよう
な構造を有しており、原子炉容器1には複数の冷却水入
口ノズル2と冷却水出口ノズル3が設けられている。こ
れらの冷却水入口ノズル2および冷却水出口ノズル3は
原子炉容器1の周方向に間隔を存して交互に配設されて
おり、冷却水入口ノズル2から原子炉容器1内に流入し
た一次冷却水は、原子炉容器1内に設けられた炉心槽4
と原子炉容器1との間に形成されたダウンカマー5内を
下降するようになっている。2. Description of the Related Art Conventionally, this type of reactor has a structure as shown in FIG. 3, and a reactor vessel 1 is provided with a plurality of cooling water inlet nozzles 2 and cooling water outlet nozzles 3. . These cooling water inlet nozzles 2 and cooling water outlet nozzles 3 are alternately arranged at intervals in the circumferential direction of the reactor vessel 1, and the primary water flowing into the reactor vessel 1 from the cooling water inlet nozzle 2 The cooling water is supplied to a core tank 4 provided in the reactor vessel 1.
The reactor 1 descends in a downcomer 5 formed between the reactor vessel 1.
【0003】炉心槽4は下端が開口した鋼製の円筒構造
物であり、ダウンカマー5内を下降した一次冷却水は炉
心槽4の下端から炉心槽4内に流入するようになってい
る。また、炉心槽4は原子炉容器1の冷却水出口ノズル
3に連通する出口管台6を有しており、炉心槽4内に流
入した一次冷却水は出口管台6から冷却水出口ノズル3
に流入し、この冷却水出口ノズル3から原子炉容器1の
外部に設けられた蒸気発生器に送られるようになってい
る。[0003] The core tank 4 is a steel cylindrical structure having an open lower end, and primary cooling water that has descended in the downcomer 5 flows into the core tank 4 from the lower end of the core tank 4. The core tank 4 has an outlet nozzle 6 communicating with the cooling water outlet nozzle 3 of the reactor vessel 1. The primary cooling water flowing into the core tank 4 is supplied from the outlet nozzle 6 to the cooling water outlet nozzle 3.
And is sent from the cooling water outlet nozzle 3 to a steam generator provided outside the reactor vessel 1.
【0004】図4は図3のA−A線に沿う断面図であ
り、同図に示す如く原子炉容器1には非常用冷却水注入
ノズル7が設けられている。この非常用冷却水注入ノズ
ル7は冷却水入口ノズル2と冷却水出口ノズル3との間
に配設されており、一次冷却水を喪失するような事故が
原子炉に発生すると、非常用冷却水注入ノズル7から原
子炉容器1内に高圧の非常用冷却水が注入されるように
なっている。FIG. 4 is a sectional view taken along the line AA of FIG. 3, and the reactor vessel 1 is provided with an emergency cooling water injection nozzle 7 as shown in FIG. The emergency cooling water injection nozzle 7 is disposed between the cooling water inlet nozzle 2 and the cooling water outlet nozzle 3, and when an accident such as loss of primary cooling water occurs in the reactor, the emergency cooling water injection nozzle 7 is provided. High-pressure emergency cooling water is injected into the reactor vessel 1 from the injection nozzle 7.
【0005】ところで、上述した非常用冷却水注入ノズ
ル7から原子炉容器1内に注入される非常用冷却水は、
原子炉容器1内の一次冷却水に比べてかなりの低温(約
20℃)であることから、非常用冷却水注入ノズル7か
ら噴出した非常用冷却水が炉心槽4の外壁面に当たる
と、炉心槽4に過大な熱応力が発生する惧れがある。こ
のため、上述した原子炉では図5に示す如く非常用冷却
水注入ノズル7と対向する炉心槽4の外壁面4aに図6
に示すような炉心槽保護パッド8を取り付け、この炉心
槽保護パッド8で非常用冷却水注入ノズル7から噴出す
る非常用冷却水を受けて炉心槽4を非常用冷却水の熱的
影響から保護するようにしている。Incidentally, the emergency cooling water injected into the reactor vessel 1 from the above-described emergency cooling water injection nozzle 7 is:
Since the temperature of the primary cooling water in the reactor vessel 1 is considerably lower than that of the primary cooling water (approximately 20 ° C.), when the emergency cooling water jetted from the emergency cooling water injection nozzle 7 hits the outer wall of the core tank 4, the core Excessive thermal stress may occur in the tank 4. For this reason, in the above-mentioned nuclear reactor, as shown in FIG.
The core tank protection pad 8 as shown in FIG. 1 is attached, and receives the emergency cooling water jetted from the emergency cooling water injection nozzle 7 to protect the core tank 4 from the thermal influence of the emergency cooling water. I am trying to do it.
【0006】[0006]
【発明が解決しようとする課題】しかしながら、非常用
冷却水注入ノズル7から噴出した非常用冷却水が上述し
た炉心槽保護パッド8に当たると、図6に示す如く非常
用冷却水の一部が原子炉容器側に向かう流れとなるた
め、原子炉容器1の内壁側で大きな温度揺らぎが発生
し、この温度揺らぎによって原子炉容器1の健全性が損
なわれる惧れがあった。また、上述した炉心槽保護パッ
ド8を炉心槽4の外壁面4aに取り付けると、炉心槽4
の外壁面4aと炉心槽保護パッド8との間に段差が生
じ、この段差によって非常用冷却水の流れが剥離等によ
って不安定な流れとなり、温度揺らぎを大きくする要因
となっていた。However, when the emergency cooling water jetted from the emergency cooling water injection nozzle 7 hits the core tank protection pad 8, the emergency cooling water is partially atomized as shown in FIG. Since the flow is directed toward the reactor vessel, large temperature fluctuations occur on the inner wall side of the reactor vessel 1, and there is a concern that the soundness of the reactor vessel 1 may be impaired by the temperature fluctuations. Further, when the above-mentioned core tank protection pad 8 is attached to the outer wall surface 4a of the core tank 4, the core tank 4
A step is generated between the outer wall surface 4a and the core tank protection pad 8, and the step causes the flow of the emergency cooling water to become unstable due to separation or the like, thereby causing a large temperature fluctuation.
【0007】本発明は上記の点に鑑みてなされたもの
で、原子炉容器側に大きな温度揺らぎを発生させること
なく炉心槽を非常用冷却水の熱的影響から保護すること
のできる原子炉を提供することを目的とするものであ
る。The present invention has been made in view of the above points, and provides a nuclear reactor capable of protecting a reactor core tank from the thermal influence of emergency cooling water without generating large temperature fluctuations on the reactor vessel side. It is intended to provide.
【0008】[0008]
【課題を解決するための手段】上記の課題を解決するた
めに、請求項1の発明は、原子炉容器内に設けられた炉
心槽の外壁面に向けて非常用冷却水を噴出する非常用冷
却水注入ノズルを備えた原子炉において、前記炉心槽の
外壁面に略円錐形状の炉心槽保護パッドを取り付け、こ
の炉心槽保護パッドの先端部を前記非常用冷却水注入ノ
ズルに対向させたことを特徴とする。請求項2の発明
は、請求項1記載の原子炉において、前記炉心槽保護パ
ッドには、前記非常用冷却水注入ノズルから噴出した非
常用冷却水を前記炉心槽の外壁面に滑らかに導く円弧状
の円錐面が形成されていることを特徴とする。In order to solve the above-mentioned problems, an invention according to a first aspect of the present invention is to provide an emergency cooling water jetting jet toward an outer wall surface of a core tank provided in a reactor vessel. In a reactor equipped with a cooling water injection nozzle, a substantially conical core tank protection pad is attached to an outer wall surface of the core tank, and a tip of the core tank protection pad is opposed to the emergency cooling water injection nozzle. It is characterized by. According to a second aspect of the present invention, in the nuclear reactor according to the first aspect, the reactor core tank protection pad has a circle for guiding the emergency cooling water spouted from the emergency cooling water injection nozzle to the outer wall surface of the reactor core tank smoothly. An arcuate conical surface is formed.
【0009】[0009]
【発明の実施の形態】以下、本発明の実施形態を図面に
基づいて説明する。図1は本発明の一実施形態に係る加
圧水型原子炉の原子炉容器と炉心槽の一部を示す縦断面
図であり、同図に示す如く原子炉容器1には非常用冷却
水注入ノズル7が設けられている。この非常用冷却水注
入ノズル7は原子炉容器1の冷却水入口ノズル2(図4
参照)と冷却水出口ノズル3との間に配設されており、
非常用冷却水注入ノズル7と対向する炉心槽4の外壁面
4aには炉心槽保護パッド10が取り付けられている。Embodiments of the present invention will be described below with reference to the drawings. FIG. 1 is a longitudinal sectional view showing a part of a reactor vessel and a core vessel of a pressurized water reactor according to an embodiment of the present invention. As shown in FIG. 7 are provided. The emergency cooling water injection nozzle 7 is connected to the cooling water inlet nozzle 2 of the reactor vessel 1 (FIG. 4).
And the cooling water outlet nozzle 3,
A core tank protection pad 10 is attached to the outer wall surface 4a of the core tank 4 facing the emergency cooling water injection nozzle 7.
【0010】炉心槽保護パッド10は非常用冷却水注入
ノズル7から原子炉容器1内に注入される非常用冷却水
の熱的影響から炉心槽4を保護するためのものであり、
炉心槽4に溶接可能な材料で形成されている。また、炉
心槽保護パッド10は図2に示す如く略円錐形状をなし
ており、その先端部10aを非常用冷却水注入ノズル7
に対向させて炉心槽4の外壁面4aに取り付けられてい
る。さらに、炉心槽保護パッド10は非常用冷却水注入
ノズル7に対向する円錐面10bを有しており、この円
錐面10bは非常用冷却水注入ノズル7から噴出した非
常用冷却水を炉心槽4の外壁面4aに滑らかに導くため
に凹状に湾曲した円弧面となっている。The core tank protection pad 10 protects the core tank 4 from the thermal influence of the emergency cooling water injected into the reactor vessel 1 from the emergency cooling water injection nozzle 7.
It is formed of a material that can be welded to the core vessel 4. The core tank protection pad 10 has a substantially conical shape as shown in FIG.
And attached to the outer wall surface 4a of the core tank 4. Further, the core tank protection pad 10 has a conical surface 10 b facing the emergency cooling water injection nozzle 7, and the conical surface 10 b discharges the emergency cooling water ejected from the emergency cooling water injection nozzle 7 into the core tank 4. Has an arcuate surface curved in a concave shape in order to smoothly guide it to the outer wall surface 4a.
【0011】上述した本発明の一実施形態では、非常用
冷却水注入ノズル7から噴出した非常用冷却水が炉心槽
保護パッド10に衝突すると、図1中矢印で示すように
非常用冷却水の流れが直線的な流れから曲線的な流れと
なり、やがて炉心槽4の外壁面4aに沿う流れとなる。In the above-described embodiment of the present invention, when the emergency cooling water ejected from the emergency cooling water injection nozzle 7 collides with the core tank protection pad 10, the emergency cooling water as indicated by an arrow in FIG. The flow changes from a linear flow to a curved flow, and eventually flows along the outer wall surface 4a of the core vessel 4.
【0012】従って、本発明の一実施形態では炉心槽保
護パッド10に衝突した非常用冷却水の一部が原子炉容
器側に向かう流れとならないため、原子炉容器側に大き
な温度揺らぎを発生させることなく炉心槽4を非常用冷
却水の熱的影響から保護することができる。また、炉心
槽4の外壁面4aと炉心槽保護パッド10との間に段差
が生じることもないので、非常用冷却水の流れが剥離等
によって不安定な流れとなることがなく、温度揺らぎの
発生要因を除去することができる。Therefore, in one embodiment of the present invention, a part of the emergency cooling water colliding with the reactor core tank protection pad 10 does not flow toward the reactor vessel side, so that a large temperature fluctuation occurs on the reactor vessel side. Without this, the core tank 4 can be protected from the thermal influence of the emergency cooling water. Also, since there is no step between the outer wall surface 4a of the core tank 4 and the core tank protection pad 10, the flow of the emergency cooling water does not become unstable due to separation or the like, and the temperature fluctuation does not occur. The cause of occurrence can be eliminated.
【0013】[0013]
【発明の効果】以上説明したように、本発明は、炉心槽
の外壁面に略円錐形状の炉心槽保護パッドを取り付け、
この炉心槽保護パッドの先端部を非常用冷却水注入ノズ
ルに対向させたことにより、原子炉容器側に大きな温度
揺らぎを発生させることなく炉心槽を非常用冷却水の熱
的影響から保護することのできる原子炉を提供できる。As described above, according to the present invention, a substantially conical core tank protection pad is attached to the outer wall surface of the core tank,
By making the tip of the core tank protection pad face the emergency cooling water injection nozzle, the core tank can be protected from the thermal effects of the emergency cooling water without generating large temperature fluctuations on the reactor vessel side. Can provide a nuclear reactor capable of operating.
【図1】本発明の一実施形態に係る加圧水型原子炉の原
子炉容器と炉心槽の一部を示す縦断面図である。FIG. 1 is a longitudinal sectional view showing a part of a reactor vessel and a core vessel of a pressurized water reactor according to an embodiment of the present invention.
【図2】本発明の一実施形態に係る加圧水型原子炉の炉
心槽に取り付けられた炉心槽保護パッドを示す図で、
(a)は正面図、(b)は側面図である。FIG. 2 is a view showing a core tank protection pad attached to a core tank of the pressurized water reactor according to one embodiment of the present invention;
(A) is a front view, (b) is a side view.
【図3】加圧水型原子炉の縦断面図である。FIG. 3 is a longitudinal sectional view of a pressurized water reactor.
【図4】図3のA−A線に沿う断面図である。FIG. 4 is a sectional view taken along line AA of FIG. 3;
【図5】従来の加圧水型原子炉の原子炉容器と炉心槽の
一部を示す縦断面図である。FIG. 5 is a longitudinal sectional view showing a part of a reactor vessel and a core vessel of a conventional pressurized water reactor.
【図6】従来の加圧水型原子炉の炉心槽に取り付けられ
た炉心槽保護パッドを示す図で、(a)は正面図、
(b)は側面図である。FIG. 6 is a view showing a core tank protection pad attached to a core tank of a conventional pressurized water reactor, (a) is a front view,
(B) is a side view.
1 原子炉容器 2 冷却水入口ノ
ズル 3 冷却水出口ノズル 4 炉心槽 6 出口管台 7 非常用冷却水
注入ノズル 10 炉心槽保護パッドDESCRIPTION OF SYMBOLS 1 Reactor vessel 2 Cooling water inlet nozzle 3 Cooling water outlet nozzle 4 Core tank 6 Outlet nozzle 7 Emergency cooling water injection nozzle 10 Core tank protection pad
───────────────────────────────────────────────────── フロントページの続き (72)発明者 中島 誠 兵庫県神戸市兵庫区和田崎町一丁目1番1 号 三菱重工業株式会社神戸造船所内 (72)発明者 朝田 誠治 兵庫県神戸市兵庫区和田崎町一丁目1番1 号 三菱重工業株式会社神戸造船所内 ──────────────────────────────────────────────────続 き Continued on the front page (72) Inventor Makoto Nakajima 1-1-1 Wadazakicho, Hyogo-ku, Hyogo-ku, Kobe-shi, Hyogo Mitsubishi Heavy Industries, Ltd. 1-1-1 Tazakicho Mitsubishi Heavy Industries, Ltd., Kobe Shipyard
Claims (2)
面に向けて非常用冷却水を噴出する非常用冷却水注入ノ
ズルを備えた原子炉において、 前記炉心槽の外壁面に略円錐形状の炉心槽保護パッドを
取り付け、この炉心槽保護パッドの先端部を前記非常用
冷却水注入ノズルに対向させたことを特徴とする原子
炉。1. A reactor equipped with an emergency cooling water injection nozzle for jetting emergency cooling water toward an outer wall surface of a core tank provided in a reactor vessel, wherein the outer wall surface of the core tank has a substantially conical shape. A reactor having a core vessel protection pad having a shape, and a front end of the core vessel protection pad facing the emergency cooling water injection nozzle.
冷却水注入ノズルから噴出した非常用冷却水を前記炉心
槽の外壁面に滑らかに導く円弧状の円錐面が形成されて
いることを特徴とする請求項1記載の原子炉。2. An arc-shaped conical surface which guides the emergency cooling water spouted from the emergency cooling water injection nozzle to the outer wall surface of the core tank is formed on the core tank protection pad. A nuclear reactor according to claim 1, characterized in that:
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP10312270A JP2000137091A (en) | 1998-11-02 | 1998-11-02 | Nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP10312270A JP2000137091A (en) | 1998-11-02 | 1998-11-02 | Nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JP2000137091A true JP2000137091A (en) | 2000-05-16 |
Family
ID=18027229
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP10312270A Withdrawn JP2000137091A (en) | 1998-11-02 | 1998-11-02 | Nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JP2000137091A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2133884A1 (en) * | 2008-03-17 | 2009-12-16 | Korea Atomic Energy Research Institute | Emergency core cooling system having core barrel injection extension ducts |
WO2019094128A3 (en) * | 2017-11-08 | 2020-03-26 | Palvannanathan Ganesan | Floating nuclear reactor protection system |
-
1998
- 1998-11-02 JP JP10312270A patent/JP2000137091A/en not_active Withdrawn
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2133884A1 (en) * | 2008-03-17 | 2009-12-16 | Korea Atomic Energy Research Institute | Emergency core cooling system having core barrel injection extension ducts |
WO2019094128A3 (en) * | 2017-11-08 | 2020-03-26 | Palvannanathan Ganesan | Floating nuclear reactor protection system |
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Legal Events
Date | Code | Title | Description |
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A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20060110 |