JPH04125497A - Heat exchanger for fast reactor - Google Patents
Heat exchanger for fast reactorInfo
- Publication number
- JPH04125497A JPH04125497A JP2244029A JP24402990A JPH04125497A JP H04125497 A JPH04125497 A JP H04125497A JP 2244029 A JP2244029 A JP 2244029A JP 24402990 A JP24402990 A JP 24402990A JP H04125497 A JPH04125497 A JP H04125497A
- Authority
- JP
- Japan
- Prior art keywords
- heat exchanger
- temperature
- fluid
- piping
- plenum
- 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
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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (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〕
本発明は原子炉の熱交換器に係り、特に、高速炉の熱交
換器で使用するに好適な熱交換器に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a heat exchanger for a nuclear reactor, and particularly to a heat exchanger suitable for use in a heat exchanger for a fast reactor.
従来の高速炉の熱交換器を含む高素炉の構造については
[日立評論VoQ0.67 NFlll(1985−
11)p、891〜892」に記述されている。Regarding the structure of a conventional fast reactor heat exchanger, see [Hitachi Review VoQ0.67 NFll (1985-
11) p., 891-892.
液体金属ナトリウム(以下、ナトリウムと記す)を冷却
材として用いるタンク型高速炉は第2図に示すように原
子炉容器9をナトリウムで満たし、その内部に炉心2.
炉心上部機構7.複数基の熱交換器1.複数基のポンプ
11が設置されている。In a tank-type fast reactor that uses liquid metal sodium (hereinafter referred to as sodium) as a coolant, as shown in FIG. 2, a reactor vessel 9 is filled with sodium, and a reactor core 2.
Upper core mechanism 7. Multiple heat exchangers1. A plurality of pumps 11 are installed.
さらに原子炉容器9内には通常の定格運転時に炉心2よ
り流出する高温のナトリウムと熱交換器1より流出する
低温のナトリウムを分離する隔壁10により原子炉容器
9内は上部の高温プレナム4と下部の低温プレナム5に
分離されている。原子炉容器9の上部はルーフスラブ1
2(蓋板)によって閉ざされている。通常の定格運転時
には、ポンプ11により循環流量が確保され、約360
℃の低温プレナムのナトリウムがポンプ11.高圧プレ
ナム3を通り、炉心2と熱交換して約530℃のナトリ
ウムとなり、高温プレナム4に流入する。高温プレナム
4のナトリウムは熱交換器1を通り、冷却されて低温プ
レナム5に流入する。原子炉が停止し、スクラムした場
合には崩壊熱除去用の熱交換器が作動し、ポニーモータ
と呼ばれる小型ポンプや原子炉内の自然循環により、原
子炉停止後の崩壊熱を除去するのに十分な定格時の10
%〜3%程度の循環流量が確保される。Furthermore, inside the reactor vessel 9, there is a partition wall 10 that separates the high temperature sodium flowing out from the reactor core 2 and the low temperature sodium flowing out from the heat exchanger 1 during normal rated operation. It is separated into a lower low temperature plenum 5. The upper part of the reactor vessel 9 is the roof slab 1
2 (lid plate). During normal rated operation, the pump 11 ensures a circulation flow rate of approximately 360
The sodium in the cold plenum at 11.℃ is pumped. It passes through the high-pressure plenum 3, exchanges heat with the reactor core 2, becomes sodium at about 530°C, and flows into the high-temperature plenum 4. The sodium in the hot plenum 4 passes through the heat exchanger 1 and is cooled before flowing into the cold plenum 5. When a nuclear reactor is shut down and scrammed, a heat exchanger for removing decay heat is activated, and a small pump called a pony motor and natural circulation inside the reactor are used to remove decay heat after the reactor shuts down. 10 when fully rated
A circulating flow rate of approximately 3% to 3% is ensured.
上記従来技術の問題点を図を用いて説明する。 The problems of the above-mentioned conventional technology will be explained using figures.
第3図は原子炉停止後の熱交換器1の出口13と低温プ
レナム5の温度T1.T2の時間変化の一例の概略を示
したものである。原子炉停止前の通常の定格運転時、高
温プレナム4の温度530℃、低温プレナム5の温度3
60℃で冷却材が循環しているとする。原子炉が停止す
ると、前記のように循環流量が急激に低下する。しかし
、熱交換器1はその内部に二次冷却系の低温流体を保有
しているため、その熱容量の影響により、スクラム初期
には流量の減少した一次系の流体を第3図に示したよう
に定格時の流出温度、即ち、低温プレナム5の温度より
も低い温度まで冷却する。−計算例では熱交換器1の二
次冷却系の熱容量の影響により第3図に示したように、
最大的100℃の温度低下を生じることになる。そして
、熱交換器1の二次冷却系と一次系の流体温度の差が少
なくなると徐々に熱交換器出口13の温度は上昇し、崩
壊熱除去用の補助熱交換器の冷却に依存した温度になる
。定格時、即ち、スクラム前には第4図(a)に示した
ようにT t = T xの温度でポンプの循環力によ
り、熱交換器出口13から低温プレナム5へ流体が流出
する。スクラム後は、上述のようにT 1 < T 2
となるため、浮力の影響により第4図(b)に示したよ
うに、熱交換器出口13からの流体は下降し、低温プレ
ナム5の流体は熱交換器出口13を通り、熱交換器1内
に流入する。熱交換器1内の温度はT1であるため、T
2の温度の流体が内部に流入して混合することにより、
第3図に概略を示したような最大変動幅ITI−T2+
の温度変動を発生する。この温度変動は熱交換器1の内
部の構造に熱サイクルや熱疲労を発生させる恐れがある
。FIG. 3 shows the temperature T1 of the outlet 13 of the heat exchanger 1 and the low temperature plenum 5 after the reactor is shut down. The figure shows an outline of an example of a change in T2 over time. During normal rated operation before reactor shutdown, the temperature of high-temperature plenum 4 is 530°C, and the temperature of low-temperature plenum 5 is 3.
Assume that the coolant is circulating at 60°C. When the nuclear reactor is shut down, the circulating flow rate decreases rapidly as described above. However, since the heat exchanger 1 contains the low-temperature fluid of the secondary cooling system inside, due to the influence of its heat capacity, the flow rate of the primary system fluid decreases at the beginning of the scram, as shown in Figure 3. It is then cooled to a temperature lower than the rated outflow temperature, that is, the temperature of the low-temperature plenum 5. - In the calculation example, as shown in Figure 3, due to the effect of the heat capacity of the secondary cooling system of heat exchanger 1,
This will result in a temperature drop of up to 100°C. Then, as the difference in fluid temperature between the secondary cooling system and the primary system of the heat exchanger 1 decreases, the temperature at the heat exchanger outlet 13 gradually increases, and the temperature depends on the cooling of the auxiliary heat exchanger for decay heat removal. become. At the rated time, that is, before scram, the fluid flows out from the heat exchanger outlet 13 to the low-temperature plenum 5 due to the circulation force of the pump at a temperature of T t =T x as shown in FIG. 4(a). After the scrum, T 1 < T 2 as mentioned above.
Therefore, due to the influence of buoyancy, the fluid from the heat exchanger outlet 13 descends as shown in FIG. flow inside. Since the temperature inside heat exchanger 1 is T1, T
By flowing the fluid at temperature 2 into the interior and mixing it,
Maximum fluctuation range ITI-T2+ as outlined in Figure 3
temperature fluctuations occur. This temperature fluctuation may cause thermal cycles or thermal fatigue to occur in the internal structure of the heat exchanger 1.
本発明の目的は、スクラム初期に、熱交換器1内への低
温プレナム5からの流体の侵入を防止し、熱交換器1内
で発生する恐れのある熱疲労を防止することにある。An object of the present invention is to prevent fluid from entering the heat exchanger 1 from the low-temperature plenum 5 at the initial stage of a scram, and to prevent thermal fatigue that may occur within the heat exchanger 1.
上記目的は、熱交換器の出口に、内部に絞りを取り付け
た配管を設け、前記絞りの下部の位置の配管面に孔を設
けることにより達成される。The above object is achieved by providing a pipe with an internal throttle installed at the outlet of the heat exchanger, and providing a hole in the pipe surface at a position below the throttle.
高速炉の熱交換器の出口に、内部に絞りを取り付けた配
管を設け、前記絞りの下部の位置の配管面に孔を設ける
ことにより、原子炉が停止し、循環流量が低下して熱交
換器出口の流体の温度が低温プレナムの流体温度よりも
低下した際、絞りは熱交換器から流出する流体を増速し
、配管の中心部を通り、低温プレナムに流出させる。そ
して、低温プレナムの熱交換器から流出する流体よりも
温度の高い流体は配管の外周に沿って配管内を上昇する
。上昇した低温プレナムからの流体は配管内面に設けら
れた絞りにより、その上昇を妨害される。しかし、この
流体の上昇は熱交換器内の流体と低温プレナムの流体の
温度差に伴う、浮力に起因するため、絞りのみでは、絞
りと配管面の間に、低温プレナムから上昇してくる流体
が溜り、やがて、絞りを乗り越えてさらに絞りよりも上
昇してしまう。そこで、本発明ではさらに絞りの下部の
配管面に孔を設け、配管内の絞りで上昇を妨害した流体
を、配管面の孔を通して配管外へ逃がすことにより、絞
りよりも上部への流体の侵入を防止する。これにより、
スクラム初期に熱交換器内に侵入した低温プレナムの流
体と熱交換器内の流体の混合に伴う温度変動を防止し、
熱疲労を防ぐことができる。At the outlet of the heat exchanger of a fast reactor, a pipe with an internal restrictor is provided, and by providing a hole in the piping surface at the bottom of the restrictor, the reactor is stopped and the circulation flow rate is reduced, allowing heat exchange. When the temperature of the fluid at the outlet drops below the fluid temperature in the cold plenum, the restriction speeds up the fluid exiting the heat exchanger and directs it through the center of the piping and out into the cold plenum. Fluid having a higher temperature than the fluid flowing out from the heat exchanger of the low temperature plenum rises inside the pipe along the outer periphery of the pipe. The rising fluid from the cold plenum is prevented from rising by a restriction provided on the inner surface of the pipe. However, this rise in fluid is caused by buoyancy due to the temperature difference between the fluid in the heat exchanger and the fluid in the low-temperature plenum. accumulates and eventually exceeds the aperture and rises even higher than the aperture. Therefore, in the present invention, a hole is further provided in the piping surface at the bottom of the restriction, and the fluid that has been prevented from rising by the restriction in the piping escapes to the outside of the piping through the hole in the piping surface, thereby preventing fluid from entering above the restriction. prevent. This results in
This prevents temperature fluctuations caused by mixing of the fluid in the heat exchanger with the fluid in the low-temperature plenum that entered the heat exchanger at the beginning of the scram.
Heat fatigue can be prevented.
以下、本発明の実施例を図面により説明する。 Embodiments of the present invention will be described below with reference to the drawings.
第1図は、本発明の高速炉用熱交換器をタンク型高速炉
の熱交換器として用いた場合の一実施例である。熱交換
器1の出口13の配管に絞り14と孔15が設けである
。原子炉が停止し、循環流量が低下して熱交換器出口1
3の流体の温度が低温プレナム5の流体温度よりも低下
した際、第5図に示すように、絞り14は熱交換器1か
ら流出する流体を増速し、出口配管工3の中心部を通り
、低温プレナム5に流出させる。そして、低温プレナム
5の熱交換器1から流出する流体よりも温度の高い流体
は出口配管13の外周に沿って配管13内を上昇する。FIG. 1 shows an example in which the fast reactor heat exchanger of the present invention is used as a heat exchanger for a tank-type fast reactor. A constriction 14 and a hole 15 are provided in the piping of the outlet 13 of the heat exchanger 1. The reactor shuts down, the circulating flow rate decreases, and the heat exchanger outlet 1
When the temperature of the fluid in the heat exchanger 3 falls below the fluid temperature in the cold plenum 5, the throttle 14 speeds up the fluid exiting the heat exchanger 1, as shown in FIG. and drain into the cold plenum 5. The fluid having a higher temperature than the fluid flowing out from the heat exchanger 1 of the low temperature plenum 5 rises inside the pipe 13 along the outer periphery of the outlet pipe 13.
上昇した低温プレナム5からの流体は配管13内面に設
けられた絞り14により、その上昇を妨害される。さら
に、絞り14の下部の配管面設けた孔15を通して絞り
14により上昇を妨害された流体を配管工3外へ逃がし
、絞り14よりも上部への流体の侵入を防止する。The rising fluid from the low-temperature plenum 5 is prevented from rising by a throttle 14 provided on the inner surface of the pipe 13. Furthermore, the fluid whose rise is blocked by the throttle 14 is allowed to escape to the outside of the plumber 3 through the hole 15 provided in the piping surface below the throttle 14, thereby preventing the fluid from entering above the throttle 14.
これにより、第6図に温度変化の概略を示すように、ス
クラム初期に熱交換器出口配管工3内に侵入した低温プ
レナム5の流体が、さらに熱交換器1内に侵入して混合
することに伴う温度変動を防止し、熱交換器1内部の構
造材の熱疲労を防ぐことができる。As a result, as shown in the outline of the temperature change in FIG. 6, the fluid in the low-temperature plenum 5 that entered the heat exchanger outlet piping 3 at the initial stage of the scram further enters the heat exchanger 1 and mixes. This can prevent temperature fluctuations caused by heat exchanger 1 and thermal fatigue of the structural materials inside the heat exchanger 1.
第7図はループ型の高速炉に本発明の熱交換器を適用し
た場合の一実施例である。原子炉容器の外部に配管で接
続された熱交換器1の容器内の二次冷却系と熱交換する
一次系流体の出口13の絞り14と孔15をもつ配管が
設けである。FIG. 7 shows an embodiment in which the heat exchanger of the present invention is applied to a loop-type fast reactor. A piping having a restriction 14 and a hole 15 is provided at the outlet 13 of the primary system fluid that exchanges heat with the secondary cooling system inside the vessel of the heat exchanger 1 which is connected to the outside of the reactor vessel by piping.
第8図は本発明のその他の実施例である。熱交換器出口
13の配管に複数の絞りと孔を設け、熱交換器1内へ低
温プレナム5からの流体が侵入するのを防ぐ構造を多重
化し、効果を高めたものである。FIG. 8 shows another embodiment of the present invention. A plurality of throttles and holes are provided in the piping of the heat exchanger outlet 13, and the structure for preventing fluid from entering the heat exchanger 1 from the low-temperature plenum 5 is multiplied, thereby increasing the effect.
本発明によれば、高速炉の熱交換器の出口に、内部に絞
りを取り付けた配管を設け、絞りの下部の□位置の配管
面に孔を設けることにより、原子炉が停止し、循環流量
が低下して熱交換器出口の流体の温度で低温プレナムの
流体温度よりも低下した際、絞りは熱交換器から流出す
る流体を増速し、配管の中心部を通り、低温プレナムに
流出させる。According to the present invention, a pipe with an internal throttle installed is provided at the outlet of the heat exchanger of a fast reactor, and a hole is provided in the piping surface at the □ position below the throttle, so that the reactor can be stopped and the circulation flow rate reduced. When the temperature of the fluid at the exit of the heat exchanger drops below the temperature of the fluid in the cold plenum, the restriction speeds up the fluid exiting the heat exchanger and directs it through the center of the piping and into the cold plenum. .
そして、低温プレナムの熱交換器から流出する流体より
も温度の高い流体は配管の外周に沿って配管内を上昇す
る。上昇した低温プレナムからの流体は配管内面に設け
られた絞りにより、その上昇を妨害される。さらに、絞
りの下部の配管面に設けた孔を通してこの流体を配管外
へ逃がし、絞りよりも上部への流体の侵入を防止できる
。これにより、スクラム初期に熱交換器内に侵入した低
温プレナムの流体と熱交換器内の流体の混合に伴う温度
変動を防止し、熱疲労を防ぐことができる。Fluid having a higher temperature than the fluid flowing out from the heat exchanger of the low temperature plenum rises inside the pipe along the outer periphery of the pipe. The rising fluid from the cold plenum is prevented from rising by a restriction provided on the inner surface of the pipe. Furthermore, this fluid can be allowed to escape from the pipe through a hole provided in the piping surface below the throttle, thereby preventing the fluid from entering above the throttle. This prevents temperature fluctuations caused by mixing of the fluid in the heat exchanger with the fluid in the low-temperature plenum that entered the heat exchanger at the initial stage of the scram, thereby preventing thermal fatigue.
第1図は本発明の一実施例の高速炉の熱交換器の説明図
、第2図はタンク型高速炉の説明図、第3図は従来技術
における原子炉停止時の熱交換器出口温度の過渡変化の
特性図、第4図は従来技術におけるスクラム前後の熱交
換器出口部の流れと温度の説明図、第5図は本発明にお
けるスクラム後の熱交換器出口部の流れと温度の説明図
、第6図は本発明における原子炉停止時の熱交換器出口
温度の過渡変化の特性図、第7図は本発明のループ型高
速炉に対する一実施例の説明図、第8図は本発明の他の
実施例の要部の説明図である。
1・・・熱交換器、2・・炉心、3・・・高圧プレナム
、4・・・高温プレナム、5・・・低温プレナム、6
・接続配管、7・・・炉心上部機構、8 ・自由液面、
9・原子炉容器、10・・・隔壁、11・・ポンプ、1
2・・ルーフスラブ、13・・・熱交換器出口、14・
・・絞り、15・・・孔、16・・・熱交換器入口。
リ乃
図
第6因
第7図Fig. 1 is an explanatory diagram of a heat exchanger of a fast reactor according to an embodiment of the present invention, Fig. 2 is an explanatory diagram of a tank-type fast reactor, and Fig. 3 is an explanatory diagram of a heat exchanger outlet temperature at reactor shutdown in a conventional technology. FIG. 4 is an explanatory diagram of the flow and temperature at the outlet of the heat exchanger before and after scram in the conventional technology, and FIG. 5 is a diagram showing the flow and temperature at the outlet of the heat exchanger after scram in the present invention. An explanatory diagram, FIG. 6 is a characteristic diagram of the transient change in the heat exchanger outlet temperature during reactor shutdown in the present invention, FIG. 7 is an explanatory diagram of an embodiment of the loop type fast reactor of the present invention, and FIG. FIG. 7 is an explanatory diagram of main parts of another embodiment of the present invention. 1... Heat exchanger, 2... Core, 3... High pressure plenum, 4... High temperature plenum, 5... Low temperature plenum, 6
・Connection piping, 7... Core upper mechanism, 8 ・Free liquid level,
9. Reactor vessel, 10... Partition wall, 11... Pump, 1
2... Roof slab, 13... Heat exchanger outlet, 14...
... Throttle, 15... Hole, 16... Heat exchanger inlet. Rino diagram 6th cause diagram 7
Claims (1)
換器において、 前記熱交換器の出口に、内部に絞りを取り付けた配管を
設け、前記絞りの下部の位置の配管面に孔を設けたこと
を特徴とする高速炉用熱交換器。 2、請求項1において、前記熱交換器の配管が前記熱交
換器に直接接続されている高速炉用熱交換器。 3、請求項1において、前記熱交換器の配管が前記熱交
換器の配管を介して熱交換器に接続されていることを特
徴とする高速炉用熱交換器。 4、請求項1において、前記熱交換器の配管が有する絞
りと孔が単数である高速炉用熱交換器。 5、請求項1において、前記熱交換器の配管が有する絞
りと孔が複数である高速炉用熱交換器。[Scope of Claims] 1. In a heat exchanger for a fast reactor in which a primary coolant is built in the reactor vessel, a pipe with a throttle installed inside is provided at the outlet of the heat exchanger, and a pipe at the bottom of the throttle is provided. A heat exchanger for a fast reactor characterized by having holes provided on the piping surface at the positions. 2. The fast reactor heat exchanger according to claim 1, wherein the piping of the heat exchanger is directly connected to the heat exchanger. 3. The heat exchanger for a fast reactor according to claim 1, wherein the piping of the heat exchanger is connected to the heat exchanger via the piping of the heat exchanger. 4. The heat exchanger for a fast reactor according to claim 1, wherein the piping of the heat exchanger has a single aperture and a single hole. 5. The heat exchanger for a fast reactor according to claim 1, wherein the piping of the heat exchanger has a plurality of apertures and holes.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2244029A JPH04125497A (en) | 1990-09-17 | 1990-09-17 | Heat exchanger for fast reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2244029A JPH04125497A (en) | 1990-09-17 | 1990-09-17 | Heat exchanger for fast reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH04125497A true JPH04125497A (en) | 1992-04-24 |
Family
ID=17112654
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2244029A Pending JPH04125497A (en) | 1990-09-17 | 1990-09-17 | Heat exchanger for fast reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH04125497A (en) |
-
1990
- 1990-09-17 JP JP2244029A patent/JPH04125497A/en active Pending
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