JPS62218891A - Double tank type fast breeder reactor - Google Patents
Double tank type fast breeder reactorInfo
- Publication number
- JPS62218891A JPS62218891A JP61060581A JP6058186A JPS62218891A JP S62218891 A JPS62218891 A JP S62218891A JP 61060581 A JP61060581 A JP 61060581A JP 6058186 A JP6058186 A JP 6058186A JP S62218891 A JPS62218891 A JP S62218891A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- cooling system
- reactor vessel
- steam generator
- fast breeder
- 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.)
- Granted
Links
- 238000001816 cooling Methods 0.000 claims description 33
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 23
- 239000002826 coolant Substances 0.000 description 34
- 239000007788 liquid Substances 0.000 description 13
- 230000000694 effects Effects 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000009434 installation Methods 0.000 description 2
- 230000000903 blocking effect Effects 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000000191 radiation 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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Other Liquid Machine Or Engine Such As Wave Power Use (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】
〔産業上の利用分野〕
本発明は、二重タンク型高速増殖炉に係シ、特に、その
原子炉容器の熱保護対策に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Industrial Field of Application] The present invention relates to a double tank type fast breeder reactor, and in particular to thermal protection measures for the reactor vessel.
従来の二重タンク型高速増殖炉の一例として、特願昭５
８−１６７１２６号に記載されている高速増殖炉の概略
構成を第３図に示す。As an example of a conventional double tank type fast breeder reactor,
FIG. 3 shows a schematic configuration of the fast breeder reactor described in No. 8-167126.
この例では、原子炉容器７の外側に２次冷却系タンク８
を設置し、原子炉容器１と同様にルーフデツキ９から吊
シ下げである。原子炉容器７と２次冷却系タンク８との
間のアニユラス部には、２次冷却系循環ポンプ１４と蒸
気発生器１とを配設し、その間に２次冷却材１６を満た
しである。２ 、次冷却材循環ポンプ１４と蒸気発生器
１とは、１次系機器七同様にルーフデツキ９から吊シ下
げてあシ、２次冷却材の流路を構成する関係上、中間熱
交換器３と同じ基数膜けである。In this example, a secondary cooling system tank 8 is installed outside the reactor vessel 7.
is installed and suspended from the roof deck 9 in the same way as the reactor vessel 1. A secondary cooling system circulation pump 14 and a steam generator 1 are disposed in the annulus between the reactor vessel 7 and the secondary cooling system tank 8, and a secondary coolant 16 is filled between them. 2. The secondary coolant circulation pump 14 and the steam generator 1 are suspended from the roof deck 9 in the same way as the primary system equipment 7, and are connected to the intermediate heat exchanger because they form a flow path for the secondary coolant. It has the same radix number as 3.
一方、原子炉容器７の内側には、炉心１９．中間熱交換
器１２．および１次主冷却系循環ポンプ１３を配設しで
ある。中間熱交換器１２と１次主冷却系循環ポンプ１３
とはルーフデツキ９から吊り下げられ、炉心１９は原子
炉容器７によシ支持されている。On the other hand, inside the reactor vessel 7, a reactor core 19. Intermediate heat exchanger12. A primary main cooling system circulation pump 13 is also provided. Intermediate heat exchanger 12 and primary main cooling system circulation pump 13
is suspended from the roof deck 9, and the reactor core 19 is supported by the reactor vessel 7.
１次冷却材１５は％１次主冷却系循環ポンプ１３によシ
炉心１９に送られ、ここで加熱されて、中間熱交換器１
２に入る。中間熱交換器１２の中では、２次冷却材１６
と熱交換して冷却され、再び１次主冷却系循壌ポンプ１
３に入る。The primary coolant 15 is sent to the reactor core 19 by the primary main cooling system circulation pump 13, heated here, and transferred to the intermediate heat exchanger 1.
Enter 2. In the intermediate heat exchanger 12, the secondary coolant 16
It is cooled by heat exchange with the primary main cooling system circulation pump 1.
Enter 3.
２次冷却材１６は、２次冷却系循環ポンプ１４によ°シ
２次冷却系タンク８から汲み上げられ、コールドレグ配
管１８を通り、ルーフデッキ９上部まで立上シ、中間熱
交換器１２の２次側に導入される。中間熱交換器１２に
入った２次冷却材１６は、１次冷却材１５との熱交換で
加熱され、２次側比ロノズルからホットレグ配管１７に
よシ蒸気発生器１に導入される。２次冷却材１６は、蒸
気発生器１内で水蒸気側に熱を伝えて流下し、２次冷却
系タンク８内に戻る。The secondary coolant 16 is pumped up from the secondary cooling system tank 8 by the secondary cooling system circulation pump 14, passes through the cold leg piping 18, rises to the top of the roof deck 9, and is pumped up into the intermediate heat exchanger 12. Introduced to the next side. The secondary coolant 16 that has entered the intermediate heat exchanger 12 is heated by heat exchange with the primary coolant 15, and is introduced into the steam generator 1 through the hot leg piping 17 from the secondary side nozzle. The secondary coolant 16 transfers heat to the steam side within the steam generator 1, flows down, and returns to the secondary cooling system tank 8.
第４図に上記従来例の蒸気発生器の概略構成を示す。給
水管２と伝熱管３は胴体２２の中に収納れている。給水
管２は、胴体２２とシュラウド５との間を下降し、シュ
ラウド５の下端で反転して、伝熱管３に接続されている
。この例では、給水管は片側に寄せられていると考えら
れるが、その外側は胴体２２で覆われておシ、原子炉容
器７とは直接対面できないようになっている。FIG. 4 shows a schematic configuration of the conventional steam generator described above. The water supply pipe 2 and the heat transfer pipe 3 are housed in the body 22. The water supply pipe 2 descends between the body 22 and the shroud 5, is inverted at the lower end of the shroud 5, and is connected to the heat exchanger pipe 3. In this example, the water supply pipe is considered to be moved to one side, but the outside thereof is covered by the body 22 so that it cannot directly face the reactor vessel 7.
上記従来技術では、原子炉容器の冷却についての配慮が
なく１次のような問題があった。The above-mentioned conventional technology does not take into consideration the cooling of the reactor vessel and has the following problems.
第５図に前記原子炉容器７の液面近傍の冷却材液位の関
係の一例を示す。原子炉容器７内では、中間熱交換器１
２の１次側圧力損失により、高温１次冷却材２３と低＠
１次冷却材２４０間にΔＨ１の液位差が生ずる。また、
２次冷°却系タンク７内においても、蒸気発生器１の２
次冷却材圧力損失によシ、高温の２次冷却材２５と低温
の２次冷却材２６との間にΔＨ２の液位差が生ずる。FIG. 5 shows an example of the relationship between the coolant liquid level near the liquid level of the reactor vessel 7. Inside the reactor vessel 7, an intermediate heat exchanger 1
Due to the pressure loss on the primary side of 2, the high temperature primary coolant 23 and low @
A liquid level difference of ΔH1 occurs between the primary coolants 240. Also,
Also in the secondary cooling system tank 7, 2 of the steam generator 1
Due to the secondary coolant pressure loss, a liquid level difference of ΔH2 occurs between the high temperature secondary coolant 25 and the low temperature secondary coolant 26.
これらの液位差のために、原子炉容器７の上部領域は、
１次カバーガス空間２７を介する高温１次冷却材２３か
らの熱輻射および２次カバーガス空間２８を介する高温
２次冷却材２５から熱輻射によ９１両側から加熱され、
著しく高温になる惧れがある。従って、原子炉容器７の
健全性確保には、何らかの冷却対策が必要である。Due to these liquid level differences, the upper region of the reactor vessel 7
Heated from both sides of 91 by thermal radiation from the high temperature primary coolant 23 via the primary cover gas space 27 and thermal radiation from the high temperature secondary coolant 25 via the secondary cover gas space 28,
There is a risk of extremely high temperatures. Therefore, to ensure the integrity of the reactor vessel 7, some kind of cooling measure is required.
本発明の目的は、原子炉容器の健全性を確保するのに充
分な冷却構造を有する二重タンク塁高速増殖炉を提供す
ることである。It is an object of the present invention to provide a double tank fast breeder reactor with sufficient cooling structure to ensure the integrity of the reactor vessel.
Ｃ問題点を解決するための手段〕
本発明は、上記目的を達成するために、蒸気発生器の給
水管の少なくとも一部を原子炉容器壁に対面させて配列
し、蒸気発生器の給水に原子炉容器壁を冷却させる手段
を提案するものである。Means for Solving Problem C] In order to achieve the above object, the present invention arranges at least a portion of the water supply pipes of the steam generator so as to face the wall of the reactor vessel, and provides water supply pipes for the steam generator. This paper proposes a means of cooling the reactor vessel wall.
この給水管は、原子炉容器側に多く、２次冷却系タンク
側に少なく配列することが好ましい。It is preferable that more water supply pipes be arranged on the reactor vessel side and fewer on the secondary cooling system tank side.
このように、原子炉容器と対面する形で配列された給水
管には、次の２つの作用がある。The water supply pipes arranged so as to face the reactor vessel have the following two effects.
（１） 原子炉容器から熱輻射によシ熱吸収する。(1) Heat is absorbed by thermal radiation from the reactor vessel.
Ｃ）蒸気発生器内の高温の２次冷却材から原子炉容器へ
の熱輻射を遮断する。C) Blocking heat radiation from the high temperature secondary coolant in the steam generator to the reactor vessel.
これらの作用により、原子炉容器の＆度を下げることが
できる。These actions make it possible to lower the temperature of the reactor vessel.
次に、第１図および第２図により１本発明の一実施例を
説明する。Next, an embodiment of the present invention will be described with reference to FIGS. 1 and 2.
第１図は本発明による二重タンク型高速増殖炉の一実施
例を示す縦断面図である。図において、蒸気発生器１は
、原子炉容器７と２次冷却系タンク８とによシ形成され
るア二二うス部に、ルーフデツキ９から吊シ下げられて
いる。蒸気発生器１に２次冷却材を導入する２次冷却材
入口管６は、蒸気発生器１の上方から挿入されておシ、
伝熱管３の上方で開口している。給水管２は、原子炉容
器７側と２次冷却系夕／り８側にｖＲシ分けて配列され
、シュラウド５の下端で反転し、伝熱管３に接続されて
いる。給水管２．伝熱管３．およびシュラクト５は、と
もに、蒸気発生器据付７ランジ２１から吊シ下げた伝熱
管サポート４によって支持されている。この伝熱管サポ
ート４は、第２図に詳細を示す通シ、リプ構造になって
いるから、給水管２が、原子炉容器７または２次冷却系
タンク８と直接対面するようになっている。FIG. 1 is a longitudinal sectional view showing an embodiment of a double tank type fast breeder reactor according to the present invention. In the figure, a steam generator 1 is suspended from a roof deck 9 in an annular space formed by a reactor vessel 7 and a secondary cooling system tank 8. The secondary coolant inlet pipe 6 that introduces the secondary coolant into the steam generator 1 is inserted from above the steam generator 1.
It opens above the heat exchanger tube 3. The water supply pipes 2 are arranged in a vR manner on the reactor vessel 7 side and the secondary cooling system tank 8 side, are inverted at the lower end of the shroud 5, and are connected to the heat exchanger tubes 3. Water supply pipe 2. Heat exchanger tube 3. and shracto 5 are both supported by heat exchanger tube supports 4 suspended from steam generator installation 7 langes 21. This heat transfer tube support 4 has a through-hole structure, the details of which are shown in FIG. 2, so that the water supply pipe 2 directly faces the reactor vessel 7 or the secondary cooling system tank 8. .
中間熱交換器１２で加熱された高温２次冷却材は、２次
冷却材入口管６から蒸気発生器ｌに入シ、シュラウド５
の内側を流下し、伝熱管３において、その内部を流れる
水と蒸気によシ冷却された後、２次冷却系タンク８の中
に入っていく。他方、低温の給水は、給水管２の中を流
れ、伝熱管３で外部を流れる２次冷却材によシ加熱され
、蒸気となって蒸気発生器１から出ていく。The high-temperature secondary coolant heated by the intermediate heat exchanger 12 enters the steam generator l from the secondary coolant inlet pipe 6, and is passed through the shroud 5.
After flowing down the inside of the heat transfer tube 3 and being cooled by the water and steam flowing inside the heat transfer tube 3, it enters the secondary cooling system tank 8. On the other hand, low-temperature feed water flows through the water supply pipe 2, is heated by the secondary coolant flowing outside in the heat transfer tube 3, and exits the steam generator 1 as steam.
原子炉通常運転中、２次冷却材の液位についてみると、
伝熱管３の部分の流動抵抗分だけ、蒸気発生器内液面１
１が２次冷却系タンク液面１０よシも相対的に盛）上が
シ、第１図に示すバランスとなっている。このため、第
２図のように配列した給水管２は、２次冷却系タンク液
面１０よシ上では、カバーガス中に露出し、原子炉容器
７とはカバーガス空間を介して対面する形となる。通常
、給水管２内には約２００Ｃ前後の給水が流れており、
他方、原子炉７側は、高温の１次冷却材により加熱され
、約５ｏｏＣ近い温度になっている。Looking at the liquid level of the secondary coolant during normal reactor operation,
The liquid level 1 in the steam generator increases by the flow resistance of the heat transfer tube 3.
1 is relatively high compared to the secondary cooling system tank liquid level 10), and the balance shown in FIG. 1 is achieved. Therefore, the water supply pipes 2 arranged as shown in FIG. 2 are exposed in the cover gas above the liquid level 10 of the secondary cooling system tank, and face the reactor vessel 7 through the cover gas space. It takes shape. Normally, water at around 200C flows in the water supply pipe 2.
On the other hand, the reactor 7 side is heated by the high temperature primary coolant and has a temperature close to about 5ooC.
従って、対面している給水管２と原子炉容器７との間に
は、約ａｏｏｔ：’の温度差があり、この大きな温度差
による熱輻射効果で、原子炉容器７を有効に冷却できる
。また、給水管２は、シュラウド５内部の高温２次冷却
材と原子炉容器７との間に配列されているので、高温２
次冷却材から原子炉容器７への熱の流れも遮断できるこ
とになる。Therefore, there is a temperature difference of about aoot:' between the water supply pipe 2 and the reactor vessel 7, which are facing each other, and the reactor vessel 7 can be effectively cooled by the heat radiation effect due to this large temperature difference. In addition, since the water supply pipe 2 is arranged between the high temperature secondary coolant inside the shroud 5 and the reactor vessel 7, the high temperature 2
The flow of heat from the secondary coolant to the reactor vessel 7 can also be blocked.
以上の効果も第１図に示す系統について評価した結果を
第６図に示す。図から明らかなように、原子炉容器７の
温度を約２０Ｇ下げることができた。The above effects were evaluated for the system shown in FIG. 1, and the results are shown in FIG. As is clear from the figure, the temperature of the reactor vessel 7 was able to be lowered by approximately 20G.
本発明によれば、原子炉容器を低温の給水管によシ冷却
できるので、原子炉容器の温度を下げ、その構造健全性
を向上させる効果が得られる。According to the present invention, since the reactor vessel can be cooled by a low-temperature water supply pipe, it is possible to lower the temperature of the reactor vessel and improve its structural integrity.
第１図は本発明による二重タンク型高速増殖炉の一実施
例を示す縦断面図、第２図はその蒸気発生器の斜視図、
第３図は従来の二重タンク型高速増殖炉の概略構成を示
す図、第４図は従来の蒸気発生器の縦断面図、第５図は
二重タンク盟高速増殖炉の液位バランス状態を示す図、
第６図は本発明と従来例の原子炉容器温度分布を比較し
て示す図である。
１・・・蒸気発生器、２・・・給水管、３・・・伝熱管
、４・・・伝熱管サポート、５・・・シュラウド、６・
・・２次冷却材入口管、７・・・原子炉容器、訃・・２
次冷却系タンク、１０・・・２次冷却系タンク液面、１
１・・・蒸気発生器内液面、１２・・・中間熱交換器、
１３・・・１次主冷却系循環ポンプ、１４・・・２次主
冷却系循環ポンプ、１５・・・１次冷却材、１６・・・
２次冷却材、１７・・・２次主冷却系ホットレグ配管、
１８・・・２次主冷却コールドレグ配管、１９・・・炉
心、２０・・・原子炉容器内液位、２１・・・蒸気発生
器据付フランジ。
２２・・・胴体、２３・・・高温１次冷却材、２４・・
・低温１次冷却材、２５・・・高温２次冷却材、２６・
・・低温２次冷却材、２７・・・１次カバーガス空間、
２８・・・２次カバーガス空間。
ぐｒ、１FIG. 1 is a longitudinal sectional view showing an embodiment of a double tank fast breeder reactor according to the present invention, and FIG. 2 is a perspective view of its steam generator.
Figure 3 is a diagram showing the schematic configuration of a conventional double tank fast breeder reactor, Figure 4 is a vertical cross-sectional view of a conventional steam generator, and Figure 5 is a liquid level balance state of a double tank fast breeder reactor. A diagram showing
FIG. 6 is a diagram showing a comparison of the reactor vessel temperature distributions of the present invention and a conventional example. DESCRIPTION OF SYMBOLS 1... Steam generator, 2... Water supply pipe, 3... Heat exchanger tube, 4... Heat exchanger tube support, 5... Shroud, 6...
...Secondary coolant inlet pipe, 7...Reactor vessel, end...2
Secondary cooling system tank, 10... Secondary cooling system tank liquid level, 1
1... Liquid level in the steam generator, 12... Intermediate heat exchanger,
13... Primary main cooling system circulation pump, 14... Secondary main cooling system circulation pump, 15... Primary coolant, 16...
Secondary coolant, 17...Secondary main cooling system hot leg piping,
18...Secondary main cooling cold leg piping, 19...Reactor core, 20...Liquid level in reactor vessel, 21...Steam generator installation flange. 22... fuselage, 23... high temperature primary coolant, 24...
・Low temperature primary coolant, 25...High temperature secondary coolant, 26・
...Low temperature secondary coolant, 27...Primary cover gas space,
28...Secondary cover gas space.
gr, 1
Claims (1)
側に２次冷却系タンクを設け、２次冷却部系タンク内で
前記原子炉容器外側の環状部分に２次冷却系循環ポンプ
と蒸気発生器とを配設した二重タンク量高速増殖炉にお
いて、前記蒸気発生器の給水で前記原子炉容器壁を冷却
するために蒸気発生器の給水管の少なくとも一部を原子
炉容器壁に対面させて配列することを特徴とする二重タ
ンク型高速増殖炉。 ２、特許請求の範囲第１項に記載の二重タンク型高速増
殖炉において、前記蒸気発生器の給水管を、前記原子炉
容器側に多く、前記２次冷却系タンク側に少なく配列す
ることを特徴とする二重タンク型高速増殖炉。[Claims] 1. A secondary cooling system tank is provided outside the reactor vessel in which the reactor core and primary cooling system equipment are installed, and within the secondary cooling system tank, 2. In a double-tank fast breeder reactor equipped with a secondary cooling system circulation pump and a steam generator, at least a portion of the water supply pipe of the steam generator is used to cool the reactor vessel wall with the water supplied from the steam generator. A double tank type fast breeder reactor characterized by arranging the reactor so as to face the wall of the reactor vessel. 2. In the double tank type fast breeder reactor according to claim 1, more water supply pipes of the steam generator are arranged on the reactor vessel side and fewer on the secondary cooling system tank side. A double tank type fast breeder reactor featuring:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61060581A JPH0656423B2 (en) | 1986-03-20 | 1986-03-20 | Double tank type fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61060581A JPH0656423B2 (en) | 1986-03-20 | 1986-03-20 | Double tank type fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62218891A true JPS62218891A (en) | 1987-09-26 |
| JPH0656423B2 JPH0656423B2 (en) | 1994-07-27 |
Family
ID=13146348
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61060581A Expired - Lifetime JPH0656423B2 (en) | 1986-03-20 | 1986-03-20 | Double tank type fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0656423B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8036335B2 (en) | 2003-03-04 | 2011-10-11 | Japan Nuclear Cycle Development Institute | Thermal load reducing system for nuclear reactor vessel |
-
1986
- 1986-03-20 JP JP61060581A patent/JPH0656423B2/en not_active Expired - Lifetime
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8036335B2 (en) | 2003-03-04 | 2011-10-11 | Japan Nuclear Cycle Development Institute | Thermal load reducing system for nuclear reactor vessel |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0656423B2 (en) | 1994-07-27 |
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