JPH04188095A - Vessel wall cooling device for reactor vessel - Google Patents
Vessel wall cooling device for reactor vesselInfo
- Publication number
- JPH04188095A JPH04188095A JP2315818A JP31581890A JPH04188095A JP H04188095 A JPH04188095 A JP H04188095A JP 2315818 A JP2315818 A JP 2315818A JP 31581890 A JP31581890 A JP 31581890A JP H04188095 A JPH04188095 A JP H04188095A
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- coolant
- cylindrical body
- annular region
- vessel wall
- 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
- 238000001816 cooling Methods 0.000 title claims abstract description 19
- 239000002826 coolant Substances 0.000 claims abstract description 33
- 239000007788 liquid Substances 0.000 claims abstract description 22
- 230000000694 effects Effects 0.000 abstract description 7
- 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 4
- 229910052708 sodium Inorganic materials 0.000 description 4
- 239000011734 sodium Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000007423 decrease Effects 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 1
- 230000000630 rising effect Effects 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は、原子炉容器の容器壁冷却装置に関するもので
ある。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a vessel wall cooling device for a nuclear reactor vessel.
（従来の技術）
従来の原子炉容器の容器壁冷却装置を第４，５図により
説明すると、第４図の（１）が自由液面（−）を有する
原子炉容器の容器壁、（２）が炉心上部構造物、（３）
が円筒体で、同円筒体（３）が上記容器壁（１）の内側
に設置されて、互いの間に円環状領域が形成されている
。また（５）が炉心、（４）が同炉心（５）上方の低圧
力のホットプレナム、（６）が上記炉心（５）下方の高
圧力のコールドプレナム、（７）が上記自由液面（Ｗ）
の上方のガス空間部で、コールドプレナム（６）の冷た
い冷却材（ナトリウム）（Ａ）の一部を分岐、減圧した
後、容器壁（１）と円筒体（３）との間に形成した円環
状領域に導き、上昇させて、原子炉容器の容器壁（１）
を冷却する。また容器壁（１）を冷却した後の冷却材（
Ａ）を円筒体（３）の上端部から自由液面（−）へ溢流
させるようになっている。(Prior Art) A conventional vessel wall cooling device for a nuclear reactor vessel will be explained with reference to FIGS. 4 and 5. In FIG. ) is the core superstructure, (3)
is a cylindrical body, and the cylindrical body (3) is installed inside the container wall (1) to form an annular region therebetween. (5) is the reactor core, (4) is the low-pressure hot plenum above the core (5), (6) is the high-pressure cold plenum below the core (5), and (7) is the free liquid level ( W)
In the upper gas space, after branching and depressurizing a part of the cold coolant (sodium) (A) in the cold plenum (6), a pipe is formed between the container wall (1) and the cylindrical body (3). The vessel wall (1) of the reactor vessel is guided into the annular region and raised.
to cool down. Also, the coolant (
A) is made to overflow from the upper end of the cylindrical body (3) to the free liquid level (-).
第５図の（Ｉ）は定格運転時の状態を示し、第５図の（
ＩＩ）はポンプ出力低下時の状態を示している。なお上
記円筒体（３）を二重、三重にしたものも従来公知であ
る。(I) in Fig. 5 shows the state during rated operation, and (I) in Fig. 5 shows the state during rated operation.
II) shows the state when the pump output decreases. In addition, those in which the above-mentioned cylindrical body (3) is doubled or tripled are also conventionally known.
（発明が解決しようとする課題）
前記第４．５図に示す従来の原子炉容器の容器壁冷却装
置には１次の問題があった。即ち。(Problems to be Solved by the Invention) The conventional reactor vessel wall cooling device shown in FIG. 4.5 has the following problem. That is.
（１）容器壁（１）を冷却する冷却材（Ａ）が円筒体（
３）の上端部から自由液面体）へ溢流する際１円周方向
に均一に落下しないため１円筒体（３）が振動を起す。(1) The coolant (A) that cools the container wall (1) is a cylindrical body (
3) When the liquid overflows from the upper end to the free liquid surface body (3), it does not fall uniformly in the circumferential direction, causing the cylindrical body (3) to vibrate.
（１１）冷却材（Ａ）の円筒体（３）上端部から自由液
面−）への落下中、ガス空間部（７）中のガスを巻き込
んで、ガスが冷却材（Ａ）に混入する。(11) While the coolant (A) is falling from the upper end of the cylinder (3) to the free liquid surface, the gas in the gas space (7) is drawn in and mixed into the coolant (A). .
（ｉｉｉ）容器壁（１）を冷却する冷却材（Ａ）がポン
プにより加圧された主流から分岐減圧されて、容器壁（
１）と円筒体（３）との間に形成した円環状領域へ導か
れるが、ポンプが低出力になった場合、圧力（ヘッド）
が足らなくて、容器壁（１）を冷却した冷却材（Ａ）が
円筒体（３）の上端部（堰）を越えられず、冷却材（Ａ
）が上記円環状領域に停滞して（第５図（ＩＩ）参照）
、容器壁（１）の冷却が不可能になるという問題があっ
た。(iii) The coolant (A) that cools the container wall (1) is branched and depressurized from the main stream pressurized by the pump, and the container wall (1) is branched and depressurized.
1) and the cylindrical body (3), but when the pump becomes low output, the pressure (head)
As a result, the coolant (A) that has cooled the container wall (1) cannot cross the upper end (weir) of the cylindrical body (3), and the coolant (A)
) stagnates in the annular region (see Figure 5 (II)).
, there was a problem that cooling of the container wall (1) became impossible.
本発明は前記の問題点に鑑み提案するものであり、その
目的とする処は１円筒体の振動を防止できる。またガス
の冷却材への巻き込み、混入を防止できる。さらにポン
プ低出力時の冷却材の円環状領域での停滞を防止できる
原子炉容器の容器壁冷却装置を提供しようとする点にあ
る。The present invention has been proposed in view of the above-mentioned problems, and its purpose is to prevent vibration of a cylindrical body. Furthermore, it is possible to prevent gas from being drawn into or mixed into the coolant. Another object of the present invention is to provide a vessel wall cooling device for a nuclear reactor vessel that can prevent coolant from stagnation in an annular region when the pump output is low.
（課題を解決するだめの手段）
上記の目的を達成するために１本発明は、自由液面を有
する原子炉容器の内側に円筒体を設置し。(Means for Solving the Problems) In order to achieve the above object, one aspect of the present invention is to install a cylindrical body inside a reactor vessel having a free liquid level.
これら原子炉容器と円筒体との間に円環状領域を形成し
て、この円環状領域に冷却材を導く原子炉容器の容器壁
冷却装置において、前記円環状領域を上昇してきた冷却
材をサイフオン効果により前記円筒体の上端部を乗り越
えさせて原子炉容器内の自由液面下へ流入させるサイフ
オン形成用カバーを前記円筒体の上端部に跨座状態に取
付けている。In vessel wall cooling devices for reactor vessels that form an annular region between the reactor vessel and the cylindrical body and guide coolant to this annular region, the coolant that has risen through the annular region is siphoned. A siphon-forming cover is attached to the upper end of the cylindrical body so as to straddle the upper end of the cylindrical body, thereby causing the liquid to flow over the upper end of the cylindrical body and below the free surface of the reactor vessel.
（作用）
本発明の原子炉容器の容器壁冷却装置は前記のように構
成されており、コールドプレナムの冷たい冷却材（ナト
リウム）の一部を分岐、：＄ｉ圧した後１原子炉容器壁
と円筒体との間に形成した円環状領域に導き、上昇させ
て、原子炉容器壁を冷却する。また原子炉容器壁を冷却
した後の円環状領域を上昇してきた冷却材をサイフオン
形成用カバーのサイフオン効果により９円筒体の上端部
を乗り越えさせて、原子炉容器内の自由液面下へ流入さ
せる。(Function) The reactor vessel wall cooling device of the present invention is configured as described above, and after branching off a part of the cold coolant (sodium) in the cold plenum and pressurizing it, and the cylindrical body, and is raised to cool the reactor vessel wall. In addition, the coolant that has risen in the annular region after cooling the reactor vessel wall is caused to overcome the upper end of the cylindrical body due to the siphon effect of the siphon-forming cover, and flows below the free liquid level in the reactor vessel. let
（実施例）
次に本発明の原子炉容器の容器壁冷却装置を第１図に示
す一実施例により説明すると、（１）が自由液面（−）
を有する原子炉容器の容器壁、（３）が円筒体で、同円
筒体（３）が上記容器壁（１）の内側に設置されて、互
いの間に円環状領域が形成されている。また（７）が上
記自由液面（Ｗ）の上方のガス空間部、（８）が本発明
で最も特徴とするサイフオン形成用カバーで、同サイフ
オン形成用カバー（８）は１容器壁（１）または円筒体
（３）に取付けられて、上記円筒体（３）の上端部を跨
いでおり、その両側下部は、上記円環状領域内の冷却材
（Ａ）及び上記円筒体（３）内の冷却材（Ａ）に浸漬し
ている。また（９）が上記サイフオン形成用カバー（８
）に取付けた真空引き用配管である。(Example) Next, the reactor vessel wall cooling device of the present invention will be explained using an example shown in FIG. 1. (1) is the free liquid level (-)
The vessel wall (3) of the reactor vessel having a cylindrical body is a cylindrical body, and the cylindrical body (3) is installed inside the vessel wall (1) to form an annular region therebetween. Further, (7) is a gas space above the free liquid level (W), and (8) is a cover for forming a siphon, which is the most characteristic feature of the present invention. ) or the cylindrical body (3), and straddles the upper end of the cylindrical body (3), and its lower sides are connected to the coolant (A) in the annular region and the inside of the cylindrical body (3). It is immersed in the coolant (A). In addition, (9) is the cover for forming the siphon (8).
) is the vacuum piping attached to the
次に前記第１図に示す原子炉容器の容器壁冷却装置の作
用を具体的に説明する。コールドプレナム（６）の冷た
い冷却材（ナトリウム）（Ａ）の一部を分岐、減圧した
後、容器壁（１）と円筒体（３）との間に形成した円環
状領域に導き、上昇させて、原子炉容器の容器壁（１）
を冷却する。また容器壁（１）を冷却した後の円環状領
域を上昇してきた冷却材（Ａ）をサイフオン形成用カバ
ー（８）のサイフオン効果により１円筒体（３）の上端
部を乗り越えさせて、原子炉容器内の自由液面（匈）下
へ流入させる。Next, the operation of the reactor vessel wall cooling device shown in FIG. 1 will be explained in detail. After branching and depressurizing a part of the cold coolant (sodium) (A) in the cold plenum (6), it is guided into an annular region formed between the container wall (1) and the cylindrical body (3) and raised. The vessel wall of the reactor vessel (1)
to cool down. In addition, the coolant (A) that has risen in the annular region after cooling the container wall (1) is caused to cross over the upper end of the cylindrical body (3) by the siphon effect of the siphon forming cover (8), and the atomic The liquid is allowed to flow below the free liquid level in the furnace vessel.
その際、真空引き用配管（９）により、サイフオン形成
用カバー（８）内を真空引きすると、上記円環状領域か
ら円筒体（３）上端部を経た原子炉容器内への流入がさ
らにスムーズに行われる。即ち。At that time, if the inside of the siphon formation cover (8) is evacuated using the vacuum piping (9), the flow from the annular region into the reactor vessel via the upper end of the cylindrical body (3) becomes even smoother. It will be done. That is.
真空引き用配管（９）により、サイフオン形成用カバー
（８）内を真空引きすると、上昇側の冷却材（Ａ）、即
ち、容器壁（１）側カバー（８）と円筒体（３）上端部
との間の冷却材（Ａ）が強制的に上昇させられ１円筒体
（３）上端部からは反転し、自重により下降して、原子
炉容器内の自由液面（圓）下へスムーズに流入する。When the inside of the siphon forming cover (8) is evacuated by the vacuum piping (9), the coolant (A) on the rising side, that is, the cover (8) on the side of the container wall (1) and the upper end of the cylindrical body (3) The coolant (A) between the cylindrical body (3) is forcibly raised, reversed from the upper end of the cylinder (3), and descended due to its own weight, smoothly below the free liquid level (circle) in the reactor vessel. flows into.
第２図（Ｉ）（ｎ）は、ループ型原子炉の例を示し、第
３図は、タンク型原子炉の例を示しているが１本発明の
容器壁冷却装置は、これらの原子炉にも適用可能である
。因みに第２図（１）の（１）は容器壁、（４）はホッ
トプレナム、（５）は炉心、（６）はコールドプレナム
である。また第２図（ＩＩ’）の（１） （４） （５
） （６）は上記と同一の部分、（６’）はコールドプ
レナムスタグナント部である。また第３図の（１） （
５） （６）は上記と同一の部分、（６’）はコールド
プレナム、 （１０）はポンプモータ、 （１１）は中
間熱交換器である。2(I)(n) shows an example of a loop type nuclear reactor, and FIG. 3 shows an example of a tank type nuclear reactor. It is also applicable to Incidentally, in Fig. 2 (1), (1) is the vessel wall, (4) is the hot plenum, (5) is the reactor core, and (6) is the cold plenum. Also, (1) (4) (5) in Figure 2 (II')
) (6) is the same part as above, and (6') is the cold plenum stagnant part. Also, (1) in Figure 3 (
5) (6) is the same part as above, (6') is the cold plenum, (10) is the pump motor, and (11) is the intermediate heat exchanger.
（発明の効果）
本発明の原子炉容器の容器壁冷却装置は前記のようにコ
ールドプレナムの冷たい冷却材（ナトリウム）の一部を
分岐、減圧した後、原子炉容器壁と円筒体との間に形成
した円環状領域に導き、上昇させて、原子炉容器壁を冷
却する。また原子炉容器壁を冷却した後の円環状領域を
上昇してきた冷却材をサイフオン形成用カバーのサイフ
オン効果により１円筒体の上端部を乗り越えさせて、原
子炉容器内の自由液面下へ流入させるので、冷却材が円
筒体の上端部から自由液面へ溢流する際。(Effects of the Invention) As described above, the reactor vessel wall cooling device of the present invention branches and depressurizes a part of the cold coolant (sodium) in the cold plenum, and then cools the space between the reactor vessel wall and the cylindrical body. The reactor vessel wall is cooled by guiding the reactor into an annular region formed in the center of the reactor and raising it to cool the reactor vessel wall. In addition, the coolant that has risen in the annular region after cooling the reactor vessel wall is caused to overcome the upper end of one cylinder due to the siphon effect of the siphon-forming cover and flow below the free liquid level in the reactor vessel. so that when the coolant overflows from the upper end of the cylinder to the free liquid surface.
円周方向に均一に落下させることができて１円筒体の振
動を防止できる。It can be made to fall uniformly in the circumferential direction, and vibration of one cylindrical body can be prevented.
また上記のように円環状領域を上昇してきた冷却材をサ
イフオン形成用カバーのサイフオン効果により１円筒体
の上端部を乗り越えさせて、原子炉容器内の自由液面下
へ流入させるので、冷却材の円筒体上端部から自由液面
への落下中、ガス空間部中のガスを巻き込むことがなく
て、ガスの冷却材への巻き込み、混入を防止できる。In addition, as mentioned above, the coolant that has ascended through the annular region is caused to overcome the upper end of one cylindrical body due to the siphon effect of the siphon-forming cover and flow below the free liquid surface in the reactor vessel. While falling from the upper end of the cylindrical body to the free liquid surface, the gas in the gas space is not dragged in, and gas can be prevented from being dragged into or mixed into the coolant.
また上記のように円環状領域を上昇してきた冷却材をサ
イフオン形成用カバーのサイフオン効果により５円筒体
の上端部を乗り越えさせて、原子炉容器内の自由液面下
へ流入させるので、ポンプ低出力時の冷却材の円環状領
域での停滞を防止できる。In addition, as mentioned above, the siphon effect of the siphon-forming cover causes the coolant that has risen in the annular region to overcome the upper end of the 5th cylinder and flow below the free liquid level in the reactor vessel, which lowers the pump. It is possible to prevent the coolant from stagnation in the annular region during output.
第１図は本発明に係わる原子炉容器の容器壁冷却装置の
一実施例を示す縦断側面図、第２図（Ｉ）（ｎ）はルー
プ型原子炉の例を示す説明図、第３図はタンク型原子炉
の例を示す説明図、第４図は従来の原子炉容器の容器壁
冷却装置を示す縦断側面図、第５図（ｒ）は定格運転時
の状態を示す説明図、第５図（Ｕ）はポンプ出力低下時
の状態を示す説明図である。
（１） ・・・原子炉容器の容器壁、（３）・・・円
筒体。
（８）・・・サイフオン形成用カバー、（す・・・自由
液面、（Ａ）・・・冷却材。FIG. 1 is a longitudinal side view showing an embodiment of the vessel wall cooling device for a reactor vessel according to the present invention, FIGS. 2(I) and (n) are explanatory diagrams showing an example of a loop type reactor, and FIG. 4 is an explanatory diagram showing an example of a tank-type nuclear reactor, FIG. 4 is a vertical cross-sectional side view showing a conventional reactor vessel wall cooling device, FIG. FIG. 5(U) is an explanatory diagram showing a state when the pump output decreases. (1) ... Vessel wall of the reactor vessel, (3) ... Cylindrical body. (8) Cover for forming a siphon, (Free liquid level, (A) Coolant.
Claims (1)
これら原子炉容器と円筒体との間に円環状領域を形成し
て、この円環状領域に冷却材を導く原子炉容器の容器壁
冷却装置において、前記円環状領域を上昇してきた冷却
材をサイフオン効果により前記円筒体の上端部を乗り越
えさせて原子炉容器内の自由液面下へ流入させるサイフ
オン形成用カバーを前記円筒体の上端部に跨座状態に取
付けたことを特徴とする原子炉容器の容器壁冷却装置。A cylindrical body is installed inside a reactor vessel with a free liquid level,
In vessel wall cooling devices for reactor vessels that form an annular region between the reactor vessel and the cylindrical body and guide coolant to this annular region, the coolant that has risen through the annular region is siphoned. A reactor vessel characterized in that a siphon-forming cover is attached to the upper end of the cylindrical body so as to straddle the upper end of the cylindrical body, thereby causing the liquid to flow over the upper end of the cylindrical body and below the free surface of the reactor vessel. vessel wall cooling system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2315818A JPH04188095A (en) | 1990-11-22 | 1990-11-22 | Vessel wall cooling device for reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2315818A JPH04188095A (en) | 1990-11-22 | 1990-11-22 | Vessel wall cooling device for reactor vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH04188095A true JPH04188095A (en) | 1992-07-06 |
Family
ID=18069928
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2315818A Pending JPH04188095A (en) | 1990-11-22 | 1990-11-22 | Vessel wall cooling device for reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH04188095A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2004093095A3 (en) * | 2003-04-16 | 2005-02-03 | Framatome Anp Gmbh | Nuclear facility and method for operating a nuclear facility |
| JP2012215475A (en) * | 2011-03-31 | 2012-11-08 | Mitsubishi Heavy Ind Ltd | Reactor vessel structure and operation method of reactor |
-
1990
- 1990-11-22 JP JP2315818A patent/JPH04188095A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2004093095A3 (en) * | 2003-04-16 | 2005-02-03 | Framatome Anp Gmbh | Nuclear facility and method for operating a nuclear facility |
| US7532699B2 (en) | 2003-04-16 | 2009-05-12 | Areva Np Gmbh | Nuclear facility and method for operating a nuclear facility |
| JP2012215475A (en) * | 2011-03-31 | 2012-11-08 | Mitsubishi Heavy Ind Ltd | Reactor vessel structure and operation method of reactor |
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