JPS6055798B2 - Drain removal device in the reactor containment vessel sandwich section - Google Patents

Drain removal device in the reactor containment vessel sandwich section

Info

Publication number
JPS6055798B2
JPS6055798B2 JP53035190A JP3519078A JPS6055798B2 JP S6055798 B2 JPS6055798 B2 JP S6055798B2 JP 53035190 A JP53035190 A JP 53035190A JP 3519078 A JP3519078 A JP 3519078A JP S6055798 B2 JPS6055798 B2 JP S6055798B2
Authority
JP
Japan
Prior art keywords
sand
reactor containment
containment vessel
shielding wall
drain
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
JP53035190A
Other languages
Japanese (ja)
Other versions
JPS54126891A (en
Inventor
潔 岡村
浩亨 船田
寿明 清水
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 Engineering Corp
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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 Toshiba Engineering Corp, Toshiba Corp, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Engineering Corp
Priority to JP53035190A priority Critical patent/JPS6055798B2/en
Publication of JPS54126891A publication Critical patent/JPS54126891A/en
Publication of JPS6055798B2 publication Critical patent/JPS6055798B2/en
Expired 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

Description

【発明の詳細な説明】 本発明は原子力発電所における原子炉格納容器サンド
クッション部のドレン抜き装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a drain removal device for a sand cushion portion of a nuclear reactor containment vessel in a nuclear power plant.

一般にサンドクッション部の砂は、事故時に格納容器
壁の局部応力を緩和させる機能を有するものであり、こ
の機能を充分発揮させるためには乾燥状態を維持するこ
とが必要である。 従来、たとえばMark−■型原子
炉格納容器のサンドクッション部ドレン抜き装置として
は、第1図及び第2図に示すように、原子炉格納容器1
を包囲する生体遮蔽壁2を貫通し原子炉格納容器1と生
体遮蔽壁2との間に設けたサンドクッション部3から原
子炉建屋内床ドレンフアンネル4a、4b、4cに至る
弁5a、5bを有する配管5をサンドクッション部3の
周面に数箇所に設けてなるものが知られている。
Generally, the sand in the sand cushion has the function of relieving local stress on the wall of the containment vessel in the event of an accident, and in order to fully utilize this function, it is necessary to maintain a dry state. Conventionally, as shown in FIGS. 1 and 2, a drain removal device for a sand cushion part of a Mark-■ type reactor containment vessel, for example, has been used to
Valves 5a, 5b penetrate through the biological shielding wall 2 surrounding the reactor containment vessel 1 and extend from the sand cushion part 3 provided between the reactor containment vessel 1 and the biological shielding wall 2 to the reactor building indoor floor drain funnels 4a, 4b, 4c. It is known that pipes 5 having the following characteristics are provided at several locations on the circumferential surface of the sand cushion portion 3.

しかしながら、この種のドレン抜き装置では、配管入口
部6からサンドクッション底部までの水は抜くことがで
きず、原子炉建屋床面上に配管を引き廻すため通路とし
ての妨げになり、またサンドクッション内の砂が徐々に
流出して、サンドクッションの機能を維持することが困
難となる。
However, with this type of drain removal device, water cannot be drained from the piping inlet 6 to the bottom of the sand cushion, and the piping is routed on the floor of the reactor building, which obstructs the passageway, and the sand cushion The sand inside gradually flows out, making it difficult to maintain the function of the sand cushion.

さらに弁5a,5bが原子炉建屋内に露出しているため
原子炉建屋内の構造が複雑となる等の欠点がある。本発
明は前記従来の欠点を解決し、何らかの原因によりサン
ドクッション部3に水が流入した場合、サンドクッショ
ン部3の砂を混入させることなく流入した水をより確実
に外部に排水することができる信頼性の高い原子炉格納
容器サンドクッション部のドレン抜き装置を提供するこ
とを目的とする。
Further, since the valves 5a and 5b are exposed inside the reactor building, there is a drawback that the structure inside the reactor building becomes complicated. The present invention solves the above-mentioned conventional drawbacks, and when water flows into the sand cushion part 3 for some reason, it is possible to more reliably drain the water to the outside without mixing the sand in the sand cushion part 3. An object of the present invention is to provide a highly reliable drain removal device for a sand cushion portion of a nuclear reactor containment vessel.

以下本発明を第3図ないし第6図に示す一実施例に基づ
いて説明する。
The present invention will be explained below based on an embodiment shown in FIGS. 3 to 6.

第3図及び第4図に示すように、原子炉格納容器1の外
周には、原子炉格納容器1と所要間隔を保持して生体遮
蔽壁2が周設されている。
As shown in FIGS. 3 and 4, a biological shielding wall 2 is provided around the outer periphery of the reactor containment vessel 1 at a required distance from the reactor containment vessel 1.

そして、この生体遮蔽壁2と原子炉格納容器1との間の
間隙の底部には、乾燥した砂が充填され、この部分にサ
ンドクッション部3を形成している。このサンドクッシ
ョン部3の下端部には、第5図に拡大して示したように
下り勾配の防砂機構100が生体遮蔽壁2のコンクリー
ト内に埋め込まれた状態で設けられている。この防砂機
構100は、第6図に拡大して示すように、砂利詰用筒
体7、防砂用スクリーン8、穴あきフランジ部材9、さ
らにドレン捕集箱10の順に連結されている。ドレン捕
集箱10にはその下面にライザー管11が突設されてお
り、このライザー管11は、第3図に示すようにサンド
クッション部3の下方位.置に傾斜して配設されたリン
グヘッダ12に連通されている。
The bottom of the gap between the biological shielding wall 2 and the reactor containment vessel 1 is filled with dry sand, forming a sand cushion portion 3 in this portion. At the lower end of the sand cushion section 3, as shown in an enlarged view in FIG. 5, a downwardly sloped sand prevention mechanism 100 is provided embedded in the concrete of the biological shielding wall 2. As shown in an enlarged view in FIG. 6, this sand prevention mechanism 100 includes a gravel filling cylinder 7, a sand prevention screen 8, a perforated flange member 9, and a drain collection box 10 connected in this order. A riser pipe 11 is protruded from the lower surface of the drain collection box 10, and the riser pipe 11 is located below the sand cushion portion 3 as shown in FIG. The ring header 12 is connected to a ring header 12 which is arranged at an angle.

リングヘッダ12は、第4図の水平断面図に示すように
原子炉格納容器1の外側に位置し、コンクリート16内
に埋め込まれている。この実施例では、リングヘッダ1
2は文字どおり−リングではなく不必要な部分を切り欠
いたものを使用している。リングヘッダ12の傾斜下端
部位置12aには、1本の配管13が連通されている(
第3図参照)。
The ring header 12 is located outside the reactor containment vessel 1, as shown in the horizontal sectional view of FIG. 4, and is embedded in concrete 16. In this example, ring header 1
2 literally uses a ring with unnecessary parts cut out instead of a ring. One pipe 13 is connected to the inclined lower end position 12a of the ring header 12 (
(See Figure 3).

この配管13はたとえば逆止弁のような逆流防止器14
を介して原子炉建屋内床の1つのブロック17にあるサ
ンプタンク15に連通されている(第4図参照)。上記
砂利詰用筒体7内には、第6図に詳細に示すように、金
網7aに詰められた砂利7bが二重の防砂用スクリーン
8に向つて次第にその粒が大きくなるように充填されて
いる。
This piping 13 is connected to a backflow preventer 14 such as a check valve.
It communicates with a sump tank 15 located in one block 17 on the floor of the reactor building (see FIG. 4). As shown in detail in FIG. 6, the gravel filling cylinder 7 is filled with gravel 7b packed in a wire mesh 7a so that the grain size gradually increases toward the double anti-sand screen 8. ing.

(本実施例では、3種類の粒度に分けてある。)また、
防砂用゛スクリーン8は、ガラスクロスまたは合成樹脂
クロスその他適当な材料て構成されており、断面ほぼI
形の耐圧用の穴あきフランジ部材9に設けられたドレン
捕集孔9aおよび前記砂利7bと相俟つて、ドレン捕集
箱10への砂の流入を防止している。なお、防砂機構1
00は、サンドクッション部3の周方向に複数設けるこ
とが好ましい。
(In this example, it is divided into three types of particle size.) Also,
The sand prevention screen 8 is made of glass cloth, synthetic resin cloth, or other suitable material, and has a cross section of approximately I
Together with the drain collection hole 9a provided in the pressure-resistant perforated flange member 9 and the gravel 7b, sand is prevented from flowing into the drain collection box 10. In addition, sand control mechanism 1
It is preferable that a plurality of numbers 00 are provided in the circumferential direction of the sand cushion portion 3.

また、原子炉建屋の地下階は、建屋内の溢水対策として
、分離壁2a,2b,2cによつてたとえば3ブロック
に系統分離され、配管破損等の事故が起つた場合でも他
のブロックに流れ込まないように構成されている。次に
上記装置の作用を説明する。
In addition, the underground floor of the reactor building is divided into, for example, three blocks by separation walls 2a, 2b, and 2c to prevent water from flooding inside the building, so that even if an accident such as a pipe breakage occurs, water will not flow into other blocks. It is configured so that it does not. Next, the operation of the above device will be explained.

原子炉格納容器サンドクッション部には、以下の如き原
因による水の流入が考えられる。
Water may enter the sand cushion portion of the reactor containment vessel due to the following reasons.

(イ)運転または建屋内空気調整条件の変化による生体
遮蔽壁2と原子炉格納容器1との間の空気が生体遮蔽壁
2および原子炉格納容器1の外壁面に結露した水。
(b) Water condensed on the outer wall surfaces of the biological shielding wall 2 and the reactor containment vessel 1 due to air between the biological shielding wall 2 and the reactor containment vessel 1 due to changes in operation or air conditioning conditions in the building.

(口)原子炉格納容器壁面に結露した水または隔離弁よ
り漏洩した水が配管を伝わつて流入した水。
(Note) Water that has condensed on the walls of the reactor containment vessel or water that has leaked from an isolation valve and has flowed in through piping.

(ハ)基礎マット外部よりコンクリート打ち継ぎ部等を
伝わつてサンドクッション部に染み込む地下水。
(c) Groundwater that seeps into the sand cushion from outside the foundation mat through concrete pour joints, etc.

これらの水は、まずサンドクッション部3下端部に溜り
、防砂機構100に流れ込む。
These waters first accumulate at the lower end of the sand cushion section 3 and flow into the sand prevention mechanism 100.

この際、砂利7bによつてある程度の砂の流出が防止さ
れ、さらに防砂スクリーン8によつて完全に砂の流出が
防止される。
At this time, the gravel 7b prevents sand from flowing out to some extent, and the sand prevention screen 8 completely prevents sand from flowing out.

ドレン捕集箱10に流れ込んだ水は、ライザー管11を
通流してリンダヘツダ12に導びかれ、さらに配管13
および逆止弁14を介してサンプタンク15に流れ込む
The water that has flowed into the drain collection box 10 flows through the riser pipe 11 and is led to the cylinder header 12, and then to the pipe 13.
and flows into the sump tank 15 via the check valve 14.

以上本発明を好適な実施例に基づいて説明したが、本発
明によれば、リングヘッダにしたことにより原子炉建屋
の地下階の系統分離の要求を高い信頼性を持つて満足す
ることができ、またドレン抜きの場所を必要に応じて容
易に増加することができる。
The present invention has been described above based on the preferred embodiments. According to the present invention, by using a ring header, the requirements for system separation in the underground floor of a reactor building can be satisfied with high reliability. Also, the number of drain locations can be easily increased as needed.

さらにサンドクッション部の水抜きが確実になるととも
に従来のように多数の弁5a,5bも不要となるのて経
済性の面でも有効である。またドレン抜きの箇所が増加
してもリングヘッダが1個でよいため、バルブの開閉操
作が全く不要になり、作業面での煩雑さを払拭すること
ができる。すなわち配管途中に逆流防止器である逆止弁
が設けられており、この弁を、ドレン捕集箱に水が溜ま
ると、その水頭で開き自動的に水は配管をサンプタンク
へ導びかれるように構成すれば、作業員による弁の開閉
操作はまつたく必要としない。
Furthermore, water can be drained from the sand cushion portion reliably, and the large number of valves 5a and 5b required in the prior art is not required, which is also effective from an economic point of view. Furthermore, even if the number of drain points increases, only one ring header is required, so there is no need to open or close valves, and the complexity of work can be eliminated. In other words, a check valve, which is a backflow preventer, is installed in the middle of the piping, and when water collects in the drain collection box, this valve opens at the head of the water and automatically guides the water through the piping to the sump tank. With this configuration, there is no need for an operator to open or close the valve.

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

第1図は従来の原子炉格納容器サンドクッション部のド
レン抜き装置の縦断面図、第2図は第1図のA−A線に
おける水平断面図、第3図ないし第6図は本発明の一実
施例を示すもので、第3図は概要縦断面図、第4図は第
3図のB−B線における水平断面図、第5図はサンドク
ッション部の下端拡大断面図、第6図は砂利詰用開口部
分の拡大断面図てある。 1・・・・・・原子炉格納容器、2・・・・・・生体遮
蔽壁、3・・・・・サンドクッション部、7・・・・・
・砂利詰用筒体、7b・・・・・・砂利、8・・・・・
・防砂用スクリーン、9・・・・・・穴あきフランジ部
材、10・・・・・・ドレン収集箱、1.2・・・・・
・リングヘッダ、13・・・・・・排水管、14・・・
・・・逆流防止器、100・・・・・・防砂機構。
FIG. 1 is a vertical sectional view of a conventional drain removal device for a sand cushion section of a reactor containment vessel, FIG. 2 is a horizontal sectional view taken along line A-A in FIG. 1, and FIGS. 3 is a schematic vertical sectional view, FIG. 4 is a horizontal sectional view taken along line B-B in FIG. 3, FIG. 5 is an enlarged sectional view of the lower end of the sand cushion part, and FIG. is an enlarged cross-sectional view of the opening for gravel filling. 1...Reactor containment vessel, 2...Biological shielding wall, 3...Sand cushion part, 7...
・Gravel filling cylinder, 7b... Gravel, 8...
- Sand control screen, 9... Perforated flange member, 10... Drain collection box, 1.2...
・Ring header, 13... Drain pipe, 14...
... Backflow preventer, 100 ... Sand prevention mechanism.

Claims (1)

【特許請求の範囲】 1 原子炉格納器と、この原子炉格納容器の外周に間隔
を保持して周設された生体遮蔽壁と、この生体遮蔽壁と
原子炉格納容器との間隙の底部に砂を充填してなるサン
ドクッション部と、このサンドクッション部の下端周面
に開口部を有し生体遮蔽壁底部に埋め込まれた複数の防
砂機構と、この各々の防砂機構に水力的に接続され生体
遮蔽壁下方付近に埋め込まれたリングヘッダと、このリ
ングヘッダから原子炉建屋内の単一のブロックに導かれ
る排水管と、この排水管に設けられた逆流防止器とを具
備したことを特徴とする原子炉格納容器サンドクッショ
ン部のドレン抜き装置。 2 防砂機構は、下流側に向けてその粒度が大きくなる
ように筒体内に充填された砂利と、この砂利の下流側に
設けられた防砂用スクリーンと、この防砂用スクリーン
の下流側に設けられた耐圧用構造物である穴あきフラン
ジ部材と、この穴あきフランジ部材の下流側に設けられ
たドレン捕集箱とを具備することを特徴とする特許請求
の範囲第1項記載の原子炉格納容器サンドクッション部
のドレン抜き装置。
[Scope of Claims] 1. A reactor containment vessel, a biological shielding wall provided around the outer periphery of the reactor containment vessel at a distance, and a biological shielding wall provided at the bottom of the gap between the biological shielding wall and the reactor containment vessel. A sand cushion portion filled with sand, a plurality of sand prevention mechanisms having an opening at the lower peripheral surface of the sand cushion portion and embedded in the bottom of the biological shielding wall, and hydraulically connected to each of the sand prevention mechanisms. Features include a ring header embedded near the bottom of the biological shielding wall, a drain pipe leading from the ring header to a single block in the reactor building, and a backflow preventer installed in the drain pipe. Drain removal device for the sand cushion section of the reactor containment vessel. 2. The sand control mechanism consists of gravel filled in a cylinder so that the particle size increases toward the downstream side, a sand control screen installed downstream of the gravel, and a sand control screen installed downstream of the sand control screen. A nuclear reactor containment according to claim 1, characterized in that the reactor containment comprises a perforated flange member which is a pressure-resistant structure, and a drain collection box provided on the downstream side of the perforated flange member. Drain removal device for container sand cushion section.
JP53035190A 1978-03-27 1978-03-27 Drain removal device in the reactor containment vessel sandwich section Expired JPS6055798B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP53035190A JPS6055798B2 (en) 1978-03-27 1978-03-27 Drain removal device in the reactor containment vessel sandwich section

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP53035190A JPS6055798B2 (en) 1978-03-27 1978-03-27 Drain removal device in the reactor containment vessel sandwich section

Publications (2)

Publication Number Publication Date
JPS54126891A JPS54126891A (en) 1979-10-02
JPS6055798B2 true JPS6055798B2 (en) 1985-12-06

Family

ID=12434925

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53035190A Expired JPS6055798B2 (en) 1978-03-27 1978-03-27 Drain removal device in the reactor containment vessel sandwich section

Country Status (1)

Country Link
JP (1) JPS6055798B2 (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5114672A (en) * 1974-07-24 1976-02-05 Mitsubishi Heavy Ind Ltd KAMOTSUSHUNOSOCHI

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5114672A (en) * 1974-07-24 1976-02-05 Mitsubishi Heavy Ind Ltd KAMOTSUSHUNOSOCHI

Also Published As

Publication number Publication date
JPS54126891A (en) 1979-10-02

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