JPS6024883B2 - How to shut off steam generators and piping in nuclear power plants - Google Patents
How to shut off steam generators and piping in nuclear power plantsInfo
- Publication number
- JPS6024883B2 JPS6024883B2 JP54035969A JP3596979A JPS6024883B2 JP S6024883 B2 JPS6024883 B2 JP S6024883B2 JP 54035969 A JP54035969 A JP 54035969A JP 3596979 A JP3596979 A JP 3596979A JP S6024883 B2 JPS6024883 B2 JP S6024883B2
- Authority
- JP
- Japan
- Prior art keywords
- steam generator
- piping
- nuclear power
- water chamber
- shut
- 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
-
- 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
Description
【発明の詳細な説明】
本発明は、原子力プラントの蒸気発生器内を点検するた
めの準備作業に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to preparatory work for inspecting the inside of a steam generator of a nuclear power plant.
第1図は、現在営業運転をしている原子力発電所の主要
部を図式的に示したものである。Figure 1 schematically shows the main parts of a nuclear power plant currently in commercial operation.
第1図において、図示しない格納容器内の相対的に低い
位置に設けられた原子炉容器1は、図示しない制御榛駆
動機構等が設けられた蓋2を有し、蒸気発生器3は前記
容器1に配管5,6を介して連絡し、配管5の途中に設
けられた循環ポンプ7と共に1次冷却材(原子炉容器1
内の発生熱を奪ってこれを冷却し、蒸気発生器3内で給
水に授熱し蒸発させる熱媒体)の循環ループ10を構成
する。In FIG. 1, a reactor vessel 1 installed at a relatively low position in a containment vessel (not shown) has a lid 2 provided with a control drive mechanism (not shown), and a steam generator 3 1 via piping 5, 6, and the primary coolant (reactor vessel 1
This constitutes a circulation loop 10 for a heat medium (heat medium) that removes the heat generated in the steam generator 3, cools it, transfers heat to the water supplied in the steam generator 3, and evaporates it.
ループ10の数は発電所の規模によって変る。蒸気発生
器3は、U字形の伝熱管9を有し、配管5,6に連絡す
る水室1 1をその下部に形成している。The number of loops 10 varies depending on the size of the power plant. The steam generator 3 has a U-shaped heat exchanger tube 9, and a water chamber 11 communicating with the pipes 5 and 6 is formed at its lower part.
原子炉容器1内には核燃料が装荷されており、所定期間
運転後、新燃料と交換したり、或いは何らかの内部点検
等を行なったりする際は、原子炉容器1の上部に形成さ
れたキャビティ13に水張りし蓋2を外して行なわれ他
方蒸気発生器3の内部点検の際には、1次冷却材(以下
冷却材という。Nuclear fuel is loaded in the reactor vessel 1, and when replacing it with new fuel after a predetermined period of operation or performing some internal inspection, a cavity 13 formed in the upper part of the reactor vessel 1 is used. When inspecting the inside of the steam generator 3 by filling it with water and removing the lid 2, the primary coolant (hereinafter referred to as coolant) is used.
)を除去して水室11及び伝熱管9を空にしてから行な
われる。しかして、前記原子炉容器1について作業と蒸
気発生器3についての作業を並行して同時に行なうこと
が、該プラントの嫁動効率を向上するために要求されて
いる。) is removed to empty the water chamber 11 and heat exchanger tubes 9. Therefore, it is required to perform the work on the reactor vessel 1 and the work on the steam generator 3 in parallel and at the same time in order to improve the efficiency of the plant.
本発明は、前記要求に鑑みなされたもので、蒸気発生器
と配管との連絡部を安全かつ確実に遮断する方法を提供
することを目的とする。The present invention was made in view of the above-mentioned requirements, and an object of the present invention is to provide a method for safely and reliably shutting off the connection between a steam generator and piping.
次に本発明を実施例に基づいて説明する。まず、原子炉
の出力運転を停止後、冷却運転ガス抜き、冷却材の浄化
運転等の作業を行った後、原子炉容器1の冷却材出入口
ノズル位置近傍の所定水位になるまで冷却材を循環ルー
プ10より部分的に抜き取り、蒸気発生器3の水室11
内を空にする。Next, the present invention will be explained based on examples. First, after stopping the output operation of the reactor, performing operations such as cooling operation degassing and coolant purification operation, the coolant is circulated until it reaches a predetermined water level near the coolant inlet/outlet nozzle position of the reactor vessel 1. Partially extracted from the loop 10, water chamber 11 of the steam generator 3
empty inside.
蒸気発生器3の水室11は、高温の冷却材が流入する部
分と低温の冷却材が流出する部分とに区別されているが
、両者共、同様の方法で遮断されるので、その一方につ
いて説明する。The water chamber 11 of the steam generator 3 is divided into a part where high-temperature coolant flows in and a part where low-temperature coolant flows out, but since both are shut off in the same way, explain.
第2図は、蒸気発生器3の水室11に関連する構造を簡
略化して示したものである。FIG. 2 shows a simplified structure related to the water chamber 11 of the steam generator 3. As shown in FIG.
前記抜き取り作業を行なうと、冷却材の水面は第2図に
示す如く配管5又は6に連絡するノズル15内の符号1
6に示す位置まで低下する。When the above-mentioned extraction operation is performed, the water surface of the coolant reaches the reference numeral 1 in the nozzle 15 connected to the pipe 5 or 6, as shown in FIG.
6.
次にマンホール18の蓋20を除去して開放する。ノズ
ル15を囲んで水茎11の内壁には、第3図に詳細に示
すように、環状座21,22,23が形成された段付の
環状サポート25が予め溶接等の適宜な手段によって固
着されている。次に第4図イに示すような円板金網(以
下金網という。)27を第4図口に示すように変形させ
て、/ズル15の内径よりも小さい内径のマンホール1
8を通過させて水室11内に搬入し、第3図に示すよう
に環状座21に着座させる。金網27は、薄くかつ弾性
に富んだ保護環27aと弾性鋼線材よりなる金網本体2
7bより構成され、第4図口のように変形させても、外
力を除けば直ちに第4図イに示す元の形状に復帰する。
しかる後に、環状シール部材即ち○リング29を第5図
口に示す如く変形させて水室11内に搬入し、第3図に
示すように金網27とサポート25の間に装着する。Next, the cover 20 of the manhole 18 is removed and opened. As shown in detail in FIG. 3, a stepped annular support 25 in which annular seats 21, 22, and 23 are formed is fixed in advance to the inner wall of the water stalk 11 surrounding the nozzle 15 by an appropriate means such as welding. ing. Next, a circular plate wire mesh (hereinafter referred to as wire mesh) 27 as shown in FIG. 4A is deformed as shown in FIG.
8 and carried into the water chamber 11, and is seated on the annular seat 21 as shown in FIG. The wire mesh 27 includes a protective ring 27a that is thin and highly elastic, and a wire mesh main body 2 made of an elastic steel wire.
7b, and even if it is deformed as shown in FIG. 4, it immediately returns to its original shape as shown in FIG. 4A, if external force is removed.
Thereafter, the annular sealing member, ie, the ring 29, is deformed as shown in the opening in FIG. 5, carried into the water chamber 11, and installed between the wire mesh 27 and the support 25 as shown in FIG.
次に第6図イに示す極めて薄い金属製の円形のシート3
1を同図口に示すように巻きこんでマンホール18を通
って水室11内へ搬入し、再び拡げて金網27及び○リ
ング29を覆って敷く。Next, a circular sheet 3 made of extremely thin metal as shown in Fig. 6A.
1 is rolled up as shown in the opening of the figure, carried into the water chamber 11 through the manhole 18, and spread out again to cover the wire mesh 27 and the circle ring 29.
シート31はその厚さに応じて複数枚重ねる。次に、絹
立てると第7図イに示すような大凡帽子状の蓋33を構
成するブロック33a,33b,33c,33d,33
eを夫々個別にマンホール18を通して水室1 1内に
搬入する。第7図口は、代表的な形状をもつブロック3
3dを示したもので、ブロック33dは、固定用ボルト
穴36が穿設された弧状フランジ部36をもつU形板3
7とフランジ部36間に設けられ合せピン穴38が穿穀
された2枚のリブ39とからなる。ブロック33a,3
3eはフランジ部にボルト穴の他にピン穴41が穿設さ
れている。蓋33をサポート25に装着するには、サポ
ート25の環状座23に楯設されたピン43をブロック
33a,33eのピン穴41に通してそのフランジ部を
環状座23に着座させ、しかる後ブロック33b,33
c,33dをそれらの間に層き、第7図イのように組立
てる。A plurality of sheets 31 are stacked according to their thickness. Next, blocks 33a, 33b, 33c, 33d, 33 that constitute a roughly hat-shaped lid 33 as shown in FIG.
e are individually carried into the water chamber 11 through the manhole 18. The opening in Figure 7 is block 3 with a typical shape.
3d, the block 33d is a U-shaped plate 3 having an arcuate flange portion 36 with fixing bolt holes 36 drilled therein.
7 and two ribs 39 provided between the flange portion 36 and having dowel pin holes 38 drilled therein. Block 33a, 3
3e has pin holes 41 drilled in the flange portion in addition to bolt holes. To attach the lid 33 to the support 25, the pin 43 mounted on the annular seat 23 of the support 25 is passed through the pin hole 41 of the blocks 33a, 33e, and the flange portion is seated on the annular seat 23, and then the block is attached. 33b, 33
Layer c and 33d between them and assemble as shown in Figure 7a.
しかる後、組合せると第8図に示すような環状の押えリ
ング48を形成すると共にボルト穴49が所要数穿穀さ
れた弧状片48a,48b,48c,48dを夫々個別
にマンホール18を通して水室11内に搬入する。Thereafter, when combined, an annular retaining ring 48 as shown in FIG. 8 is formed, and the arc-shaped pieces 48a, 48b, 48c, and 48d, each having a required number of bolt holes 49, are individually passed through the manhole 18 into the water chamber. 11.
ボルト穴49の外にピン穴50を有する弧状片48a,
48dを先ず、ピン43に通して、蓋33のフランジ部
に重ね合せ、更に弧状片48b,48cを蓋33のフラ
ンジ部に重ね合せて、第8図のように粗立てる。そして
前記蓋33の隣接するブロックのリブのピン穴38にピ
ン45を核入して、これらを一体化する。最後に、ボル
ト穴35,49を通してボルト51をサポート25のね
じ穴に螺着して蓋33及びリング48を同時にサポート
25に固定する。蓋33及びリング48を固定すること
により、前記0リング29は若干押しつぶされて、環状
座22、サポート25の内壁面及びシート31に適切な
面圧を以って密着する。an arcuate piece 48a having a pin hole 50 outside the bolt hole 49;
48d is first passed through the pin 43 and placed on the flange portion of the lid 33, and then the arcuate pieces 48b and 48c are placed on the flange portion of the lid 33 and roughened as shown in FIG. Then, a pin 45 is inserted into the pin hole 38 of the rib of the adjacent block of the lid 33 to integrate them. Finally, the lid 33 and ring 48 are fixed to the support 25 at the same time by screwing the bolts 51 into the screw holes of the support 25 through the bolt holes 35 and 49. By fixing the lid 33 and the ring 48, the O-ring 29 is slightly compressed and comes into close contact with the annular seat 22, the inner wall surface of the support 25, and the seat 31 with appropriate surface pressure.
前記した本実施例によれば、まず最初に金網27を挿着
するので作業中誤って作業工具やその他の物を配管5中
の冷却材中に落す事を防止しうると共に0リング29及
びシート31により、適切なシール性能が得られ、循環
ループの他の部分に冷却材を再充填しても蒸気発生器3
内へ冷却材が漏出することを完全に防止することができ
、ひいては蒸気発生器3の内部点検保守作業と原子炉容
器1についての作業を同時に行なうことができる。According to the present embodiment described above, since the wire mesh 27 is first inserted, it is possible to prevent work tools and other objects from accidentally falling into the coolant in the pipe 5 during work, and also to prevent the O-ring 29 and the sheet from falling into the coolant in the pipe 5. 31 provides adequate sealing performance and allows the steam generator 3
It is possible to completely prevent the coolant from leaking into the reactor vessel, and as a result, the internal inspection and maintenance work of the steam generator 3 and the work on the reactor vessel 1 can be performed at the same time.
なお、前記実施例においては、遮断に用いる各部材を組
立順に分けて水室11内に搬入したが、水室1 1の形
状、大きさ等に応じ搬入作業を同時に行ってもよいこと
は勿論である。In the above embodiment, each member used for shutoff was carried into the water chamber 11 in the order of assembly, but it is of course possible to carry them in at the same time depending on the shape, size, etc. of the water chamber 11. It is.
第1図は原子力プラントの要部を示す配置図、第2図は
蒸気発生器の水室の部分を示す概略断面図、第3図は、
本発明の実施例により遮断した状態を示す断面図、第4
図イ,口は金網27の斜視図、第5図イ,口は○リング
29の斜視図、第6図イ及び口はシート31及びシート
31をまるめた状態を夫々示す斜視図、第7図イは蓋3
3が組立てられた状態を示す斜視図、第7図口は蓋33
の構成するブロックの1つを示す斜視図、第8図は押え
リングの組立状態を示す斜視図である。
1・・・・・・原子炉容器、3・・・・・・蒸気発生器
、5,6・・・・・・配管、9・・・・・・伝熱管、1
0・・・…ループ、11......水室、′15..
…・ノズル、16・・・・・・水面、18……マンホー
ル、20……姿、21,22,23・・・・・・環状座
、25・・・・・・サポート、27・・・・・・円板金
絹、29……○リング、31……シート、33……蓋、
33a〜33e……フロツク、35……ボルト穴、36
・・・・・・フランジ部、37・・・・・・U形板、3
8……ピン穴、、3 9……リブ、4 1……ピン穴
、43……ピン、46……ピン、48……押えリング、
49……ボルト穴、50……ピン穴。
弟′図第4図
第5図
第2図
第3図
舞う図
第7図
第8図Figure 1 is a layout diagram showing the main parts of a nuclear power plant, Figure 2 is a schematic sectional view showing the water chamber of the steam generator, and Figure 3 is a
Sectional view showing a state of interruption according to the embodiment of the present invention, No. 4
Figure A, the opening is a perspective view of the wire mesh 27, Figure 5 A, the opening is a perspective view of the circle ring 29, Figure 6 A and the opening are a perspective view showing the sheet 31 and the state in which the sheet 31 is rolled up, respectively, and Figure 7. A is lid 3
3 is a perspective view showing the assembled state, Figure 7 The opening is the lid 33
FIG. 8 is a perspective view showing one of the blocks constituting the presser ring, and FIG. 8 is a perspective view showing the assembled state of the presser ring. 1... Reactor vessel, 3... Steam generator, 5, 6... Piping, 9... Heat exchanger tube, 1
0...Loop, 11. .. .. .. .. .. Water room, '15. ..
... Nozzle, 16 ... Water surface, 18 ... Manhole, 20 ... Figure, 21, 22, 23 ... Annular seat, 25 ... Support, 27 ... ...Disc metal silk, 29...○ ring, 31...sheet, 33...lid,
33a-33e...Flock, 35...Bolt hole, 36
...Flange part, 37...U-shaped plate, 3
8...pin hole, 3 9...rib, 4 1...pin hole, 43...pin, 46...pin, 48...presser ring,
49...Bolt hole, 50...Pin hole. Little brother figure 4 figure 5 figure 2 figure 3 dancing figure 7 figure 8
Claims (1)
発生器を有する原子力プラントにおいて、該蒸気発生器
内から1次冷却材を除去し、該蒸気発生器の水室のマン
ホールを開放し、該水室の配管連絡部に円板金網を挿着
し、同金網の周囲に環状シール部材を装着し、しかる後
前記金網とシール部材を覆つて組立蓋を装着することを
特徴とする原子力プラントの蒸気発生器と配管の遮断方
法。1. In a nuclear power plant that has a reactor vessel and a steam generator connected to the same vessel via piping, the primary coolant is removed from the steam generator and the manhole in the water chamber of the steam generator is opened. , a nuclear power plant characterized in that a circular metal mesh is inserted into the piping connection part of the water chamber, an annular sealing member is installed around the metal mesh, and then an assembly lid is installed to cover the metal mesh and the sealing member. How to shut off steam generators and piping in plants.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP54035969A JPS6024883B2 (en) | 1979-03-27 | 1979-03-27 | How to shut off steam generators and piping in nuclear power plants |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP54035969A JPS6024883B2 (en) | 1979-03-27 | 1979-03-27 | How to shut off steam generators and piping in nuclear power plants |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS55128701A JPS55128701A (en) | 1980-10-04 |
JPS6024883B2 true JPS6024883B2 (en) | 1985-06-15 |
Family
ID=12456751
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP54035969A Expired JPS6024883B2 (en) | 1979-03-27 | 1979-03-27 | How to shut off steam generators and piping in nuclear power plants |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6024883B2 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4667701A (en) * | 1984-12-27 | 1987-05-26 | Nuclear Energy Systems, Inc. | Nozzle dam assembly |
-
1979
- 1979-03-27 JP JP54035969A patent/JPS6024883B2/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
JPS55128701A (en) | 1980-10-04 |
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