JPS59108986A - Fbr reactor container - Google Patents

Fbr reactor container

Info

Publication number
JPS59108986A
JPS59108986A JP57218348A JP21834882A JPS59108986A JP S59108986 A JPS59108986 A JP S59108986A JP 57218348 A JP57218348 A JP 57218348A JP 21834882 A JP21834882 A JP 21834882A JP S59108986 A JPS59108986 A JP S59108986A
Authority
JP
Japan
Prior art keywords
cooling
reactor vessel
sparger
uniform
reactor
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
Application number
JP57218348A
Other languages
Japanese (ja)
Inventor
魚谷 正樹
勝久 関根
池内 壽昭
河島 弘明
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Central Research Institute of Electric Power Industry
Hitachi Ltd
Original Assignee
Central Research Institute of Electric Power Industry
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Central Research Institute of Electric Power Industry, Hitachi Ltd filed Critical Central Research Institute of Electric Power Industry
Priority to JP57218348A priority Critical patent/JPS59108986A/en
Publication of JPS59108986A publication Critical patent/JPS59108986A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Exhaust Gas After Treatment (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壁冷却方式に係り、特に、炉壁全周
にわたる均一な冷却に好適なFBR原子炉容器に関する
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor vessel wall cooling system, and particularly to an FBR reactor vessel suitable for uniform cooling over the entire circumference of the reactor wall.

第1図に従来の原子炉構造図を示す。Figure 1 shows a structural diagram of a conventional nuclear reactor.

原子炉容器1の中に炉心2が置かれる。コールドプール
3のナトリウムは、ルーフスラブ4より吊シ下げられた
ポンプ5に吸い込まれ、高圧プレナム6に行き炉心2を
通り高温となってホットプール7に入シ、中間熱交換器
で熱交換した後、コールドプール3に戻る。
A reactor core 2 is placed inside a reactor vessel 1 . The sodium in the cold pool 3 is sucked into the pump 5 suspended from the roof slab 4, goes to the high-pressure plenum 6, passes through the reactor core 2, reaches a high temperature, enters the hot pool 7, and undergoes heat exchange in an intermediate heat exchanger. Afterwards, return to Cold Pool 3.

従って原子炉容器1の上部温度は特別な配慮をしないと
、ホットグールアのナトリウムと同じ程度まで上がって
しまい、その温度は500C前後にもなるため構造強度
上好ましくない。
Therefore, unless special consideration is taken, the temperature of the upper part of the reactor vessel 1 will rise to the same level as that of sodium in hot glua, and the temperature will reach around 500C, which is not desirable in terms of structural strength.

そこで、従来は、原子炉容器1とホットプール7の間に
断熱構造9と冷却パス10を設け、冷却パス10には、
高圧ブレナム6内の低温ナトリウムを導いて対処してい
た。このナトリウムは、コールドプールのナトリウムを
ポンプで加圧したものでかつ、炉心を通さずにバイパス
させであるので、その温度は350C前後にまで冷却で
きる。
Therefore, conventionally, a heat insulating structure 9 and a cooling path 10 are provided between the reactor vessel 1 and the hot pool 7, and the cooling path 10 has the following features:
The problem was dealt with by directing low-temperature sodium inside the high-pressure Blenheim 6. This sodium is pressurized from the cold pool using a pump, and is bypassed without passing through the reactor core, so its temperature can be cooled to around 350C.

ところで、例えばタンクff1FBRの場合、原子炉容
器径は20m以上もあシ、周方向温度の不均一による変
形等の害を避けるため、炉壁冷却方式には、均一冷却性
能が要求される。
By the way, in the case of the tank ff1FBR, for example, the diameter of the reactor vessel is 20 m or more, and uniform cooling performance is required for the reactor wall cooling system in order to avoid damage such as deformation due to non-uniform circumferential temperature.

従来の冷却パス10においては、その流路断面の一辺が
極端に長いという構造上、均一冷却に必要な均一流量の
確保が離しい。
In the conventional cooling path 10, it is difficult to ensure a uniform flow rate necessary for uniform cooling due to the structure in which one side of the flow path cross section is extremely long.

本発明の目的は、周方向に同一な冷却性能を得られる冷
却方式を有する原子炉容器を提供することにある。
An object of the present invention is to provide a nuclear reactor vessel having a cooling system that can obtain uniform cooling performance in the circumferential direction.

本発明は、従来の炉壁冷却性能すなわち冷却流量が周方
向に不均一になる原因が、冷却ナト、リウムの流路41
面の一辺が非常に大きいためであることに着目して、流
路にスパージャを設置することにより均一な流量を確保
するものである。
The present invention solves the problem that the cause of the conventional furnace wall cooling performance, that is, the cooling flow rate being non-uniform in the circumferential direction, is
Taking note of the fact that one side of the surface is very large, a sparger is installed in the flow path to ensure a uniform flow rate.

第2図に、不発明実施例の炉壁冷却パスを、又、第3図
にスパージャを示す。
FIG. 2 shows the furnace wall cooling path of the non-inventive embodiment, and FIG. 3 shows the sparger.

第2図には、原子炉容器1と断熱構造9、冷却パス10
、それにバイパス11とスパージャエ2を示す。
Figure 2 shows a reactor vessel 1, a heat insulating structure 9, and a cooling path 10.
, and also shows the bypass 11 and the sparge 2.

本実施例は、炉壁冷却バス10の入口すなわち下部にス
パージャを設置した例であシ、スパージャに設けられた
多数の開口部からの噴流によシ、原子炉容器周方向の均
一冷却性能を得ようというものである。このスパージャ
の設置箇所は、第1図の高圧ブレナム6の出口すなわち
、炉壁冷却用バイパス11の入口でも同様の効果が得ら
れる。
This embodiment is an example in which a sparger is installed at the entrance, that is, at the bottom of the reactor wall cooling bath 10. Uniform cooling performance in the circumferential direction of the reactor vessel is achieved by the jet flow from a large number of openings provided in the sparger. It's about getting something. This sparger can be installed at the outlet of the high-pressure blemish 6 shown in FIG. 1, that is, at the inlet of the furnace wall cooling bypass 11, to achieve the same effect.

その場合の実施例を第4図に、第5図にスパージャを示
す。この時には、バイパス11は管ではなく、炉壁冷却
バス10と同様な構造つまり二重コーン構造となる。
An example in that case is shown in FIG. 4, and a sparger is shown in FIG. At this time, the bypass 11 is not a pipe but has a structure similar to that of the furnace wall cooling bath 10, that is, a double cone structure.

以上本実施例によれば、原子炉容器壁の全周にわたる均
一流量が確保でき、均一冷却が可能である。
As described above, according to this embodiment, a uniform flow rate can be ensured over the entire circumference of the reactor vessel wall, and uniform cooling is possible.

本発明によれば、原子炉容器壁の冷却において、周方向
の温度を均一にする効果がある。
According to the present invention, in cooling the reactor vessel wall, there is an effect of making the temperature uniform in the circumferential direction.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は原子炉構造図、第2圀は本発明の一実施例を示
す図、第3図は本発明一実施例のスパージャ説明図、第
4図は本発明の他の実施例を示す図、第5図は本発明の
他の実施例のスパージャ説明図である。 1・・・原子炉容器、lo・・・炉壁冷却バス、11・
・・炉壁冷却用バイパス、12・・・スパージャ。
Fig. 1 is a structural diagram of a nuclear reactor, Fig. 2 is a diagram showing an embodiment of the present invention, Fig. 3 is an explanatory diagram of a sparger in an embodiment of the invention, and Fig. 4 is a diagram showing another embodiment of the invention. FIG. 5 is an explanatory diagram of a sparger according to another embodiment of the present invention. 1... Reactor vessel, lo... Reactor wall cooling bath, 11.
...Furnace wall cooling bypass, 12...Sparger.

Claims (1)

【特許請求の範囲】[Claims] 1、FBR原子炉容器において、炉壁冷却パスにスパー
ジャを設けたことを特徴とするFB几原子炉容器。
1. An FB nuclear reactor vessel characterized in that a sparger is provided in the reactor wall cooling path in the FBR reactor vessel.
JP57218348A 1982-12-15 1982-12-15 Fbr reactor container Pending JPS59108986A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57218348A JPS59108986A (en) 1982-12-15 1982-12-15 Fbr reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57218348A JPS59108986A (en) 1982-12-15 1982-12-15 Fbr reactor container

Publications (1)

Publication Number Publication Date
JPS59108986A true JPS59108986A (en) 1984-06-23

Family

ID=16718460

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57218348A Pending JPS59108986A (en) 1982-12-15 1982-12-15 Fbr reactor container

Country Status (1)

Country Link
JP (1) JPS59108986A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5121117A (en) * 1974-08-16 1976-02-20 Sebukon Eng Ltd
JPS5763484A (en) * 1980-10-03 1982-04-16 Tokyo Shibaura Electric Co Nuclear reactor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5121117A (en) * 1974-08-16 1976-02-20 Sebukon Eng Ltd
JPS5763484A (en) * 1980-10-03 1982-04-16 Tokyo Shibaura Electric Co Nuclear reactor

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