JPS6360357B2 - - Google Patents
Info
- Publication number
- JPS6360357B2 JPS6360357B2 JP58129791A JP12979183A JPS6360357B2 JP S6360357 B2 JPS6360357 B2 JP S6360357B2 JP 58129791 A JP58129791 A JP 58129791A JP 12979183 A JP12979183 A JP 12979183A JP S6360357 B2 JPS6360357 B2 JP S6360357B2
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- flow path
- plug
- reactor
- water
- 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
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
- Fuel-Injection Apparatus (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
- Pressure Vessels And Lids Thereof (AREA)
- Taps Or Cocks (AREA)
Description
【発明の詳細な説明】
本発明は、出力運転中に燃料交換を行なう必要
があるような圧力管型原子炉において、その圧力
管延長部に挿入される放射線の遮蔽プラグの改良
に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement in a radiation shielding plug inserted into a pressure tube extension in a pressure tube nuclear reactor that requires fuel exchange during power operation. .
圧力管型原子炉においては、高温・高圧の冷却
材に伴う圧力を支えるため、燃料集合体と冷却材
を適当な太さの圧力管に納めたものを多数配列す
ることによつて炉心が構成される。そして、該圧
力管の端部は、シールプラグと呼ばれる栓で高
温・高圧水を外に漏洩させない構造となつてい
る。この場合、出力運転中の燃料交換を可能とす
るには、シールプラグの内側に接する放射線の遮
蔽プラグの中心に、それを縦貫する如く冷却材注
入用の小孔を設け、燃料交換時に燃料交換機から
冷却材をこの小孔に用いて注入し、再循環系の高
温水が逆流しないように工夫されている。ところ
が、この冷却材注入用の小孔は、再循環水の入口
管の上方まで通じているため、通常運転時には一
次冷却材である再循環水がこの小孔を通つてシー
ルプラグの上部に流れ込んでしまい、シール部の
温度を上昇し、シール材の寿命が短くなるという
欠点が生じる。 In a pressure tube reactor, in order to support the pressure associated with high temperature and high pressure coolant, the reactor core is constructed by arranging a large number of fuel assemblies and coolant contained in pressure tubes of appropriate diameter. be done. The end of the pressure pipe is equipped with a plug called a seal plug to prevent high-temperature, high-pressure water from leaking outside. In this case, in order to enable fuel exchange during output operation, a small hole for injecting coolant should be provided in the center of the radiation shielding plug, which is in contact with the inside of the seal plug, and run vertically through it. Coolant is injected through this small hole to prevent high-temperature water from flowing back into the recirculation system. However, this small hole for injecting coolant extends above the recirculating water inlet pipe, so during normal operation, recirculating water, which is the primary coolant, flows through this small hole to the top of the seal plug. This has the drawback of increasing the temperature of the sealing part and shortening the life of the sealing material.
原子炉出力運転中の燃料交換を計画しない場合
には、このような冷却材注入用小孔を設ける必要
がないため、シールプラグのシール材の温度を低
く保たせることが可能であるが、前述の如く運転
中に燃料交換を行なう場合には必ず冷却水注入用
小孔を設ける必要がある。従つて、将来実用炉等
において出力運転中の燃料交換を行なわねばなら
ない場合に備え、冷却水注入用小孔を設け且つシ
ール部の温度を低く維持できるような機構の開発
が強く望まれている。 If fuel exchange is not planned during reactor power operation, there is no need to provide such a small hole for injecting coolant, so it is possible to keep the temperature of the sealing material of the seal plug low. When exchanging fuel during operation, it is necessary to provide a small hole for injecting cooling water. Therefore, in preparation for the future when fuel must be exchanged during power operation in a commercial reactor, etc., there is a strong desire to develop a mechanism that can provide a small hole for injecting cooling water and maintain the temperature of the seal part low. .
本発明の目的は、上記のような従来技術の欠点
に鑑み、その技術的課題を解決する有効な機構を
提供することにあり、燃料交換時において冷却材
の注入を可能とすると共に、通常運転時に高温の
再循環水がシールプラグの上部に流れ込むのを阻
止し、それによつてシール部の温度を低く維持す
ることができ、安全性、保守性、並びに経済性を
著しく向上させることができるような改良された
圧力管型原子炉用遮蔽プラグを提供することにあ
る。 SUMMARY OF THE INVENTION In view of the drawbacks of the prior art as described above, an object of the present invention is to provide an effective mechanism for solving the technical problems. This prevents hot recirculating water from flowing to the top of the seal plug, thereby keeping the seal temperature low, significantly improving safety, maintainability, and economy. An object of the present invention is to provide an improved shielding plug for a pressure tube type nuclear reactor.
この様な目的を達成すべく案出された本発明
は、遮蔽プラグ本体を縦貫する冷却材注入用流路
の中途にボール弁機構を設けたもので、該ボール
弁機構は通常運転時に再循環水の動圧によつて前
記流路を閉塞させる方向に作動するように構成さ
れている。 The present invention, devised to achieve such an object, is provided with a ball valve mechanism in the middle of the coolant injection flow path that runs vertically through the shielding plug body, and the ball valve mechanism prevents recirculation during normal operation. It is configured to operate in the direction of closing the flow path by the dynamic pressure of water.
以下、図面に基づき本発明について更に詳しく
説明する。第1図は圧力管型原子炉の燃料取換え
口側の圧力管延長部を示す説明図である。図示さ
れていないが、圧力管3の上部は更に上方に延長
されており、その内部に燃料集合体が収納される
構造である。そして、周知の如く、高温・高圧の
冷却水は、圧力管3の下方側部に形成されている
入口管1を通つて該圧力管3内に流入し、その内
部を上昇しつつ燃料集合体と熱交換を行ない、炉
内で沸騰して蒸気と水の二相流となり、圧力管の
上部の出口管から一次冷却系の上昇管を通つて蒸
気ドラムに至るようになつている。 Hereinafter, the present invention will be explained in more detail based on the drawings. FIG. 1 is an explanatory diagram showing a pressure tube extension on the fuel exchange port side of a pressure tube nuclear reactor. Although not shown, the upper part of the pressure pipe 3 extends further upward, and the fuel assembly is housed inside the upper part of the pressure pipe 3. As is well known, the high-temperature, high-pressure cooling water flows into the pressure pipe 3 through the inlet pipe 1 formed at the lower side of the pressure pipe 3, and rises inside the pressure pipe 3 to form the fuel assembly. The steam and water are boiled in the furnace, forming a two-phase flow of steam and water, which flows from the outlet pipe at the top of the pressure pipe through the riser pipe of the primary cooling system to the steam drum.
燃料取換え口側の圧力管延長部には、図示され
ているように、遮蔽プラグ本体7とシールプラグ
9とが組込まれている。遮蔽プラグ本体7は、炉
心からの放射線(中性子線やガンマ線)を遮蔽す
るためのものであり、その構造は概ねステンレス
製のブロツク状である。また、シールプラグ9
は、再循環系の高温・高圧水を外に漏洩させない
為の栓で、シール材8が装着されたシール部を有
する構造である。 As shown in the figure, a shield plug body 7 and a seal plug 9 are incorporated in the pressure pipe extension on the fuel exchange port side. The shielding plug body 7 is for shielding radiation (neutron beams and gamma rays) from the core, and its structure is generally in the shape of a block made of stainless steel. Also, the seal plug 9
is a stopper for preventing high-temperature, high-pressure water from leaking outside from the recirculation system, and has a structure that includes a sealing part to which a sealing material 8 is attached.
炉の出力運転を停止することなしに燃料集合体
の交換を行なう場合には、燃料交換機への高温再
循環水の流入を防止するため、遮蔽プラグ本体7
を縦貫する如く冷却材注入用流路が形成される。
この冷却材注入用流路6の上端は、再循環水の入
口管1の近傍で開口する。そして、本発明が従来
技術と顕著に相違する点は、前記冷却材注入用流
路6の中途にボール弁機構5を組込んだ点であ
る。このボール弁機構5は、通常運転時に再循環
水の動圧によつて該流路6を閉塞させる方向に作
動するよう設計されている。また、ボールには遮
蔽プラグにさびつかないような材質が選択され
る。 When replacing the fuel assembly without stopping the output operation of the reactor, the shielding plug body 7 must be installed to prevent hot recirculated water from entering the fuel exchanger.
A coolant injection channel is formed so as to extend vertically through the tube.
The upper end of this coolant injection channel 6 opens in the vicinity of the recirculation water inlet pipe 1 . The present invention is significantly different from the prior art in that a ball valve mechanism 5 is incorporated in the middle of the coolant injection channel 6. This ball valve mechanism 5 is designed to operate in the direction of closing the flow path 6 by the dynamic pressure of the recirculated water during normal operation. Also, the ball is made of a material that will not rust on the shielding plug.
次に、本装置の動作とそれによつてもたらされ
る効果について説明する。先ず、原子炉出力運転
時に燃料交換を行なう場合には、燃料交換機側か
ら冷却材注入用流路6を用い冷却材を注入する。
高圧冷却水の注入によつて、ボール弁機構5のボ
ール5aは浮上し、冷却水は主流路6aから放射
方向に配設された複数の分岐流路6bを通つて圧
力管3の内部に注入される。つまり、この時冷却
水注入に対してはボール5aが浮上するため、そ
の流れは全く妨げられず、従来同様に冷却水の注
入を行なえるのである。これに対し、燃料交換作
業が終了したのち、つまり、通常運転時において
は、高温・高圧の再循環水による動圧が、前記放
射方向に配設された分岐流路6bからボール弁機
構5に作用し、そのボール5aを下方に押付ける
ため、流路6は閉塞され、その結果高温・高圧の
再循環水がシールプラグ9へと流れ込むのを防止
することができる。これによつて、シール材8の
温度は著しく低下し、シール材の寿命が飛躍的に
伸びる結果となる。第2図は圧力管の内面温度に
ついて従来技術と本発明との比較を示すグラフで
ある。ボール弁機構のない従来の場合を破線で示
し、ボール弁機構のある本発明の場合を実線で示
す。シール位置における圧力管内面温度について
見ると、従来技術では230℃程度であつたのに対
し、本発明によれば110℃程度にまで低下してい
る。シール材8は通常チタン合金であるため、こ
れによつて経済性及び運転の保守性の面が非常に
有利となる。 Next, the operation of this device and the effects brought about by it will be explained. First, when performing fuel exchange during reactor power operation, coolant is injected from the fuel exchanger side using the coolant injection channel 6.
By injecting high-pressure cooling water, the ball 5a of the ball valve mechanism 5 floats, and the cooling water is injected into the pressure pipe 3 from the main flow path 6a through a plurality of branch flow paths 6b arranged in the radial direction. be done. In other words, since the ball 5a floats in response to the injection of cooling water at this time, the flow is not obstructed at all, and the injection of cooling water can be carried out in the same manner as in the conventional case. On the other hand, after the fuel exchange operation is completed, that is, during normal operation, dynamic pressure due to high temperature and high pressure recirculated water is applied to the ball valve mechanism 5 from the branch flow path 6b arranged in the radial direction. In order to press the ball 5a downward, the flow path 6 is closed, and as a result, high temperature and high pressure recirculated water can be prevented from flowing into the seal plug 9. As a result, the temperature of the sealing material 8 is significantly lowered, resulting in a dramatic increase in the life of the sealing material. FIG. 2 is a graph showing a comparison between the prior art and the present invention regarding the inner surface temperature of the pressure tube. The conventional case without a ball valve mechanism is shown by a broken line, and the case of the present invention with a ball valve mechanism is shown by a solid line. Looking at the pressure tube inner surface temperature at the sealing position, it was about 230°C in the prior art, but it was reduced to about 110°C according to the present invention. Since the sealing material 8 is usually a titanium alloy, this provides great advantages in terms of economy and operational maintainability.
本発明は、上記のように構成した圧力管型原子
炉用遮蔽プラグであるから、冷却水注入が可能で
あるため原子炉運転中における燃料交換が可能と
なり、実用炉等で極めて有利であるし、通常運転
時に一次冷却材である高温の再循環水がシールプ
ラグの上部に流れ込むのを防止し、シール部温度
を大幅に低下させることが可能となるため、シー
ル材の寿命を著しく長くすることができ、原子炉
の安全性、保守性、及び経済性等の全て面におい
て優れた効果を奏し得るものである。 Since the present invention is a shielding plug for a pressure tube type nuclear reactor configured as described above, it is possible to inject cooling water, making it possible to exchange fuel during reactor operation, which is extremely advantageous in practical reactors, etc. During normal operation, high temperature recirculated water, which is the primary coolant, is prevented from flowing into the upper part of the seal plug, making it possible to significantly lower the seal temperature, significantly extending the life of the seal material. It is possible to achieve excellent effects in all aspects of nuclear reactor safety, maintainability, and economic efficiency.
第1図は本発明の一実施例を示す説明図、第2
図は従来技術と本発明との圧力管内面温度の比較
を示すグラフである。
1……入口管、3……圧力管、5……ボール弁
機構、6……冷却材注入用流路、7……遮蔽プラ
グ本体、8……シール材、9……シールプラグ。
FIG. 1 is an explanatory diagram showing one embodiment of the present invention, and FIG.
The figure is a graph showing a comparison of pressure tube inner surface temperatures between the prior art and the present invention. DESCRIPTION OF SYMBOLS 1... Inlet pipe, 3... Pressure pipe, 5... Ball valve mechanism, 6... Channel for coolant injection, 7... Shielding plug body, 8... Seal material, 9... Seal plug.
Claims (1)
遮蔽プラグにおいて、該遮蔽プラグの本体下部を
縦貫して上方に延びる主流路と該主流路から分岐
して該圧力管延長部の再循環水入口管近傍に開口
する分岐流路とからなる冷却材注入用流路の中途
の該分岐流路の分岐部分に、原子炉通常運転時に
該分岐流路から流入する再循環水の動圧によつて
該主流路を閉塞させる方向に作動するボール弁機
構を設けることを特徴とする圧力管型原子炉用遮
蔽プラグ。1. In a shielding plug inserted into a pressure pipe extension of a pressure tube reactor, there is a main flow passage that extends vertically through the lower part of the main body of the shield plug and extends upward, and a recirculation flow branching from the main flow passage in the pressure pipe extension. The dynamic pressure of the recirculated water that flows from the branch flow path during normal reactor operation is applied to the branch part of the coolant injection flow path, which consists of a branch flow path that opens near the water inlet pipe. A shielding plug for a pressure tube type nuclear reactor, characterized in that it is provided with a ball valve mechanism that operates in a direction to close the main flow path.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58129791A JPS6021484A (en) | 1983-07-16 | 1983-07-16 | Shielding plug for pressure-tube type reactor |
| CA000458677A CA1224282A (en) | 1983-07-16 | 1984-07-11 | Shield plug for pressure tube in pressure tube type nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58129791A JPS6021484A (en) | 1983-07-16 | 1983-07-16 | Shielding plug for pressure-tube type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6021484A JPS6021484A (en) | 1985-02-02 |
| JPS6360357B2 true JPS6360357B2 (en) | 1988-11-24 |
Family
ID=15018313
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58129791A Granted JPS6021484A (en) | 1983-07-16 | 1983-07-16 | Shielding plug for pressure-tube type reactor |
Country Status (2)
| Country | Link |
|---|---|
| JP (1) | JPS6021484A (en) |
| CA (1) | CA1224282A (en) |
-
1983
- 1983-07-16 JP JP58129791A patent/JPS6021484A/en active Granted
-
1984
- 1984-07-11 CA CA000458677A patent/CA1224282A/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6021484A (en) | 1985-02-02 |
| CA1224282A (en) | 1987-07-14 |
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