JPS60152995A - Nuclear power plant - Google Patents
Nuclear power plantInfo
- Publication number
- JPS60152995A JPS60152995A JP59008491A JP849184A JPS60152995A JP S60152995 A JPS60152995 A JP S60152995A JP 59008491 A JP59008491 A JP 59008491A JP 849184 A JP849184 A JP 849184A JP S60152995 A JPS60152995 A JP S60152995A
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- piping
- reactor vessel
- heat exchanger
- couplant
- 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.)
- Pending
Links
- 239000002826 coolant Substances 0.000 claims description 46
- 238000006073 displacement reaction Methods 0.000 description 5
- 238000009434 installation Methods 0.000 description 5
- 238000001816 cooling Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 230000002093 peripheral effect Effects 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
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
Landscapes
- Saccharide Compounds (AREA)
- Low-Molecular Organic Synthesis Reactions Using Catalysts (AREA)
- Steroid Compounds (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
本発明は原子炉容器、冷却材循環ポンプ、及び熱交換器
をもつ原子カプラント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 nuclear couplant having a reactor vessel, a coolant circulation pump, and a heat exchanger.
従来の前記原子カプラントを第１図により説明すると、
（α）が格納容器、（ｂ）ｂ−原子力容器、（Ｃ）（１
）が１次系冷却材配管、（ｄ）が１次系冷却材循環ポン
プ、（−１が中間熱交換器で、これらの機器（ｈ）〜（
ｆ）が格納容器（α）内に分散配置されて、原子炉容器
（ｂ）と１次系冷却材循環ポンプ（ｄ）と中間熱交換器
りとが１次系冷却材配管（Ｃ）（イ）によりつながれて
いる。The conventional atomic couplant will be explained with reference to FIG.
(α) is the containment vessel, (b) b-nuclear vessel, (C) (1
) is the primary coolant pipe, (d) is the primary coolant circulation pump, (-1 is the intermediate heat exchanger, and these devices (h) to (
f) are distributed in the containment vessel (α), and the reactor vessel (b), the primary coolant circulation pump (d), and the intermediate heat exchanger are connected to the primary coolant pipe (C) ( connected by b).
前記原子カプラントでは、冷却材が高温であることと各
機器にオーステナイト系ステンレス鋼を使用しているこ
ととにより、各機器及び冷却材配管の熱膨張量が大きく
て、冷却材配管にこの熱膨張量を吸収するための長大な
引廻しを必要としていた。冷却材として用いられている
ナトリウムは、中性子の照射により放射化するので、前
記原子カプラントでは、中間熱交換器（−）を１つ入れ
て、冷却系を１次系、２次系の２つの系統に分けている
が、この放射化した１次系全体の各機器を収容している
格納容器（α）も前記冷却材配管の引廻しにより、大型
化を余儀なくされており、これが原子カプラントのコス
ト高を招く主要原因になっている。In the above-mentioned nuclear coupler, because the coolant is at a high temperature and each device is made of austenitic stainless steel, the amount of thermal expansion of each device and the coolant piping is large. This required a long route to absorb the volume. Sodium, which is used as a coolant, becomes radioactive when irradiated with neutrons, so in the above-mentioned atomic couplant, one intermediate heat exchanger (-) is installed, and the cooling system is divided into two systems, a primary system and a secondary system. However, the containment vessel (α) that houses each component of the entire activated primary system has to be enlarged due to the routing of the coolant piping, and this is due to the fact that the nuclear couplant This is a major cause of high costs.
本発明は前記の問題点に対処するもので、原子炉容器、
冷却材循環ポンプ、及び熱交換器をもつ原子カプラント
において、前記各機器をつなぐ冷却材配管の両端を自由
端として同各機器内の冷却材領域に開口させ、同配管と
同各機器のケーシングとの間をベローズにより閉じたこ
とを特徴とする原子カプラントに係り、その目的とする
処は、冷却材配管を短かくすることができ、各機器の据
付けも非常に簡単に行なうことができて、設備費、据付
コスト、配置縮少に伴なう周辺設備の簡略化、建物費用
の削減を達成できる改良された原子カプラントを供する
点にある。The present invention addresses the above problems and includes a reactor vessel,
In an atomic couplant having a coolant circulation pump and a heat exchanger, both ends of the coolant piping connecting each of the devices are opened into the coolant area in each device as free ends, and the piping and the casing of each device are connected as free ends. The atomic couplant is characterized by having a bellows closed between the parts, and its purpose is to shorten the length of the coolant piping and to make the installation of each device very easy. The object of the present invention is to provide an improved atomic coupler that can reduce equipment costs, installation costs, simplify peripheral equipment due to reduced layout, and reduce building costs.
次に本発明の原子カプラントを第２．６図に示す一実施
例により説明する。まず本原子カプラントの冷却材系統
の概略を第２図により説明すると、（１）は原子炉容器
、（２）は中間熱交換器、（３）は１次系冷却材循環ポ
ンプ、（４）は１次系冷却材配管、（５）は蒸気発生器
、（６）は２次系冷却材循環ポンプ、（力は２次系冷却
材配管である。次に本原子カプラントの要部を第３図に
より説明する。同第６図は、原子炉容器（１）と中間熱
交換器（２）とこれらの機器（１）（２）をつなぐ１次
系冷却材配管（４）との１次系統を例示している。が、
本原子カプラントは、この例に限らず、２次系統等にも
適用できる。上記第６図において、（１）は原子炉容器
、（２）は中間熱交換器、（４）はこれらの機器（１）
（２）をつなぐ１次系冷却材配管、（６）（７）が上記
機器（１）（２）の蓋で、上記１次系冷却材配管（４）
の両端（自由端）は、上記蓋（６１（７１に設けた開口
部を通して上記各機器（１）（２）内へ挿入されて、同
各機器（＋１（２１内の冷却材中に開口している。なお
蓋（６）（７）に設けた開口部は配管（４）の外径より
も大きくなっている。（８）は配管（４）のサポート、
（９）は上記蓋（６！（７１と配管（４）との間（上記
機器＜１１（２）内の冷却材（液体）の上面を覆う不活
性ガス空間部と外部との間）を閉じるベローズである。Next, the atomic couplant of the present invention will be explained with reference to an embodiment shown in FIG. 2.6. First, the outline of the coolant system of this nuclear coupler plant will be explained using Figure 2. (1) is the reactor vessel, (2) is the intermediate heat exchanger, (3) is the primary coolant circulation pump, and (4) is the reactor vessel. is the primary coolant piping, (5) is the steam generator, (6) is the secondary coolant circulation pump, (power is the secondary coolant piping.) Next, we will explain the main parts of this atomic coupler. This will be explained with reference to Figure 3. Figure 6 shows the reactor vessel (1), intermediate heat exchanger (2), and primary coolant piping (4) connecting these devices (1) and (2). The following system is exemplified.
The present atomic couplant is not limited to this example, but can also be applied to secondary systems, etc. In Figure 6 above, (1) is the reactor vessel, (2) is the intermediate heat exchanger, and (4) is these devices (1).
(2), the primary system coolant pipes (6) and (7) are the lids of the above equipment (1) and (2), and the above primary system coolant pipes (4)
Both ends (free ends) of are inserted into each of the devices (1) and (2) through the openings provided in the lid (61 (71), and opened into the coolant in each device (+1 (21)). The openings provided in the lids (6) and (7) are larger than the outer diameter of the pipe (4). (8) is a support for the pipe (4),
(9) is between the above-mentioned lid (6! It is a bellows that closes.
次に前記原子カプラントの作用を説明する。配管（４）
は、原子炉容器（１）内と中間熱交換器（２）内の冷却
材中にその先端開口部が没入するように挿入されている
ため、冷却材配管（４）内のガスが一旦排出されて、冷
却材配管（４）内が冷却材で満されると、冷却材配管（
４）が上記機器（１）（２＋をつなぐ連通管になり、中
間熱交換器（２）内の冷却劇が冷却材循環ポン子炉容器
（１）内の冷却材が冷却材配管（４）の開口部（自由端
）ａＯ）から吸出され、中間熱交換器（２）内の冷却材
配管（４）の開口部（自由端）ａｌ）から吐出されて、
その後の冷却材は、原子炉容器（１）→中間熱交換器（
２）→１次系冷却材循環ポンプ（３）→原子炉容器（１
）に循環する。冷却材配管（４）と原子炉容器（１）と
中間熱交換器（２）とは常温から運転温度に至るまでの
間にそれぞれが熱膨張して、それぞれの間に相対的変位
を生じるが、前記のように構成されており、それぞれが
自由に伸縮する一方、ベローズ（９）が変形し、上記各
機器（１）（２）と配管（４）との相対的変位が吸収さ
れて、機能上にいささかの不都合も生じな〜為。Next, the action of the atomic couplant will be explained. Piping (4)
is inserted so that its tip opening is immersed in the coolant in the reactor vessel (1) and intermediate heat exchanger (2), so that the gas in the coolant pipe (4) is temporarily discharged. When the inside of the coolant pipe (4) is filled with coolant, the coolant pipe (4) is filled with coolant.
4) becomes a communication pipe that connects the above equipment (1) (2+), and the cooling action in the intermediate heat exchanger (2) is the coolant circulation. The coolant in the Ponko reactor vessel (1) is the coolant pipe (4). is sucked out from the opening (free end) aO), and discharged from the opening (free end) al) of the coolant pipe (4) in the intermediate heat exchanger (2),
After that, the coolant flows from the reactor vessel (1) to the intermediate heat exchanger (
2) → Primary coolant circulation pump (3) → Reactor vessel (1
). The coolant piping (4), the reactor vessel (1), and the intermediate heat exchanger (2) each undergo thermal expansion from room temperature to operating temperature, causing relative displacement between them. , is configured as described above, and while each expands and contracts freely, the bellows (9) deforms and absorbs the relative displacement between the above-mentioned devices (1), (2) and the piping (4), There may be some inconvenience regarding functionality.
本発明の原子カプラントは前記のように構成されており
、次の効果を達成できる。即ち、原子炉容器（１）及び
中間熱交換器（２）と配管（４）とが溶接等により剛に
結合されていないため、熱膨張による相対的変位を配管
（４）を引廻すことによって吸収する必要がない。従っ
て原子炉容器（１）と中間熱交換器（２）とを他の制限
（例えばサポー１造の強度とか遮蔽とかの制限）因子で
決められる相対位置まで近づけて配置することができて
、配管（４）を短かくすることができる。しかも短かく
なった配管（４）は、上記各機器（１）（２）を据付け
たあとで上部からこれに挿入設欝するだけでよく、従来
のように現地で溶接により接続組立てる必要がない。さ
らに従来配管系に用いられてきたハンガー、スナバ−等
の配管支持装置が極端に少なくて済む、以上のように本
発明では、冷却側配管を短かくすることができ、各機器
の据付けも非常に簡単に行なうことができて、設備費、
据付コスト、配置縮少に伴なう周辺設備の簡略化、建物
費用の削減を達成できる効果がある。The atomic couplant of the present invention is configured as described above, and can achieve the following effects. That is, since the reactor vessel (1), intermediate heat exchanger (2), and piping (4) are not rigidly connected by welding or the like, relative displacement due to thermal expansion can be reduced by routing the piping (4). No need to absorb. Therefore, the reactor vessel (1) and the intermediate heat exchanger (2) can be placed close to each other in relative positions determined by other limiting factors (for example, limitations such as the strength of the support structure and shielding), and the piping (4) can be shortened. In addition, the shorter piping (4) can be simply inserted into the above equipment (1) and (2) from above after installation, and there is no need to assemble the connections on-site by welding as in the past. . Furthermore, the number of piping support devices such as hangers and snubbers that have been conventionally used in piping systems can be extremely reduced.As described above, the present invention allows the cooling side piping to be shortened, and the installation of each device is extremely easy. It is easy to carry out, equipment costs are low,
This has the effect of reducing installation costs, simplifying peripheral equipment due to reduced layout, and reducing building costs.
第６図は自由液面をもつ機器同志を配管によりつなぐ例
を示しているが、第４図は、機器内の密閉区隔されたプ
レナムを配管によりつなぐ場合の例、即ち、１次系冷却
材ポンプ（３）と原子炉容器（１）とを配管（４）によ
りつなぐ場合の例を示している。Figure 6 shows an example in which equipment with a free liquid level is connected by piping, while Figure 4 shows an example in which a sealed plenum within the equipment is connected by piping, that is, primary system cooling. An example is shown in which a material pump (3) and a reactor vessel (1) are connected by a pipe (4).
１次系冷却材循環ポンプ（３）の吐出ブレナム（３つか
ら送り出された冷却材は、同プレナムに開口している配
管（４）の開口部（自由端）ｈから配管（４１へ送り出
され、原子炉容器（１）の高圧プレナム（１つ内に開ロ
した配管（４）の開口部（自由端） （１０’）から吐
出される。配管（４）と原子炉容器（１）及び冷却材循
環ポンプ（３）の！（６１（７）との間に生じる相対的
変位がベローズ（９）の変形により吸収されるのは前記
実施例と同じである。本実施例では、配管（４）と各ゾ
レナム側接続管（４１）（４つとが短管（４α） （４
ｂ）を介してつながっており、管（４） （４α）（４
つ、及び管（４Ｊ 、（４ｂ） （４つの間は、ピスト
ンリング等の相対変位を吸収できる可撓継手を介して結
合されている。The coolant sent out from the discharge plenum (3) of the primary coolant circulation pump (3) is sent out to the pipe (41) from the opening (free end) h of the pipe (4) that opens to the same plenum. , is discharged from the opening (free end) (10') of the pipe (4) which is open in the high pressure plenum (1) of the reactor vessel (1).The pipe (4) and the reactor vessel (1) and As in the previous embodiment, the relative displacement that occurs between the coolant circulation pump (3) and the !(61 (7)) is absorbed by the deformation of the bellows (9). In this embodiment, the piping ( 4) and each solenum side connecting pipe (41) (4 and short pipe (4α) (4
b) and are connected via tubes (4) (4α) (4
(4J, (4b)) (The four are connected via a flexible joint that can absorb relative displacement of piston rings, etc.
以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものではなく、本発
明の精神を逸脱しない範囲内で種々の設計の改変を施し
うるものである。Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .
第１図は従来の原子カプラントを示す平面図、第２図は
本発明に係る原子カプラントの冷却材系統の槻略を示す
説明図、第３図は同原子カプラントの要部の一実施例を
示す側面図、第４図は同要部の他の実施例を示す側ｍ）
図である。
（１）・・・原子炉容器、（２）・・・中間熱交換器、
（３）・・・１次冷却材循環ポンプ、（４）・・・１次
冷却材配管、（５）・・・蒸気発生器、（６）・・・２
次冷却材循環ポンプ、（７）・・・２次冷却材配管、（
９）・・・ベローズ。
復代理人 弁理士 岡 本 重 文
外３名
第２図
第３図FIG. 1 is a plan view showing a conventional atomic couplant, FIG. 2 is an explanatory diagram showing a schematic diagram of the coolant system of the atomic couplant according to the present invention, and FIG. 3 is an embodiment of the main part of the atomic couplant. Figure 4 is a side view showing another embodiment of the same main part.
It is a diagram. (1)...Reactor vessel, (2)...Intermediate heat exchanger,
(3)...Primary coolant circulation pump, (4)...Primary coolant piping, (5)...Steam generator, (6)...2
Secondary coolant circulation pump, (7)... Secondary coolant piping, (
9)...Bellows. Sub-Agent Patent Attorney Shige Okamoto 3 persons Figure 2 Figure 3
Claims (1)
子カプラントにおいて、前記各機器をつなぐ冷却材配管
の両端を自由端として同各様器内の冷却材領域に開口さ
せ、同配管と同各機器のケーシングとの間をベローズに
より閉じたことを特徴とする原子カプラント。In a nuclear couplant that has a reactor vessel, a coolant circulation pump, and a heat exchanger, both ends of the coolant piping that connects each of the above equipment are opened into the coolant area in the same vessel as free ends, and the same piping is used. An atomic couplant characterized in that the space between each device and the casing is closed by a bellows.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59008491A JPS60152995A (en) | 1984-01-23 | 1984-01-23 | Nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59008491A JPS60152995A (en) | 1984-01-23 | 1984-01-23 | Nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60152995A true JPS60152995A (en) | 1985-08-12 |
Family
ID=11694583
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59008491A Pending JPS60152995A (en) | 1984-01-23 | 1984-01-23 | Nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60152995A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0394766U (en) * | 1990-01-16 | 1991-09-26 |
-
1984
- 1984-01-23 JP JP59008491A patent/JPS60152995A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0394766U (en) * | 1990-01-16 | 1991-09-26 |
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