JPS6027395B2 - Reactor support structure cooling system - Google Patents
Reactor support structure cooling systemInfo
- Publication number
- JPS6027395B2 JPS6027395B2 JP54123874A JP12387479A JPS6027395B2 JP S6027395 B2 JPS6027395 B2 JP S6027395B2 JP 54123874 A JP54123874 A JP 54123874A JP 12387479 A JP12387479 A JP 12387479A JP S6027395 B2 JPS6027395 B2 JP S6027395B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- support structure
- space
- air
- reactor support
- 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.)
- Expired
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Cooling Or The Like Of Electrical Apparatus (AREA)
Description
【発明の詳細な説明】
本発明は原子炉支持構造体の冷却装置に係り、特に、下
方支持縦層圧力管原子炉支持構造体等に使用するに好適
な冷却装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a cooling device for a nuclear reactor support structure, and more particularly to a cooling device suitable for use in a lower support longitudinal pressure tube reactor support structure.
最初に第1図に関連して下方支持縦鷹圧力管型原子炉に
おける原子炉支持構造体の冷却構造の従来例を説明する
。First, a conventional example of a cooling structure for a reactor support structure in a downwardly supported vertical pressure tube type nuclear reactor will be described with reference to FIG.
原子炉1は原子炉支持コンクリート2のべデスタル2′
で下方より支持されており、原子炉下部空間3は深いビ
ットに蓋をした形となっている。The reactor 1 is the vedestal 2' of the reactor support concrete 2.
The reactor lower space 3 is in the form of a deep bit covered with a lid.
従って、一次系高温機器配管4からの伝熱により空気が
昇溢されると、原子炉下部に高温空気が滞留し、コンク
リートが100〜200午○の高温になる。コンクリー
トはその健全性を保つために通常運転時の温度を65℃
以下とする必要があるので、空気循環用の給気ダクトお
よび排気ダクト6が設けられているが保温部村7等で囲
まれた原子炉下部狭隣空間8の空気滞留を無くすために
は、ダクト設備が極めて複雑となるという問題点があっ
た。特に燃料交換を下方から行なう場合、原子炉下部に
は、燃料交換機9の走行用の広いスペースをとる必要が
あり、ダクト設備の簡素化が要求されている。本発明の
目的は、原子炉下部における高温ガスの滞留を防止する
ことにある。Therefore, when air rises and overflows due to heat transfer from the primary system high-temperature equipment piping 4, the high-temperature air stays in the lower part of the reactor, and the concrete reaches a high temperature of 100 to 200 pm. To maintain the integrity of concrete, the temperature during normal operation is 65℃.
Although the supply air duct and exhaust duct 6 for air circulation are provided, in order to eliminate air stagnation in the narrow adjacent space 8 at the bottom of the reactor surrounded by the heat insulation section 7 etc., it is necessary to do the following: There was a problem in that the duct equipment was extremely complicated. In particular, when fuel exchange is performed from below, it is necessary to provide a large space in the lower part of the reactor for the fuel exchange machine 9 to run, and duct equipment is required to be simplified. An object of the present invention is to prevent high-temperature gas from stagnation in the lower part of a nuclear reactor.
本発明の特徴は、原子炉支持構造体と原子炉との間に存
在する環状空間と原子炉より下方の下部空間とを連絡す
る連絡通路を、原子炉支持構造体に設けたことにある。A feature of the present invention is that the reactor support structure is provided with a communication passage that connects the annular space existing between the reactor support structure and the reactor to the lower space below the reactor.
以下本発明を図面に基づいて説明する。第2図、第3図
は本発明を下方支持縦暦圧力管型原子炉支持構造体に適
用した場合の一実施例を示すもので、原子炉プラントは
原子炉支持コンクリート2のべデスタル2′に支持され
た原子炉1′前記原子炉支持コンクリート2の外部から
原子炉下部空間3内に導入されかつ所定機器に取り付け
られた一次系高温機器配管4、図示省略の空調ユニット
に接続された給気ダクト5、保温部材7、原子炉下部狭
腿空間8、燃料交換機9、ソールプレート11等を備え
ている。The present invention will be explained below based on the drawings. FIGS. 2 and 3 show an embodiment in which the present invention is applied to a downwardly supported longitudinal pressure tube type reactor support structure. The reactor 1' supported by It includes an air duct 5, a heat insulating member 7, a narrow space 8 in the lower part of the reactor, a fuel exchanger 9, a sole plate 11, and the like.
前記給気ダクト5からは空気吐出口10,10′を通じ
て原子炉下部空間3内に冷気が吹き込まれ、その冷気で
原子炉支持コンクリート2を冷却しうるようになってい
る。Cold air is blown into the lower reactor space 3 from the air supply duct 5 through air discharge ports 10 and 10', and the reactor support concrete 2 can be cooled with the cold air.
前記原子炉下部空間3と原子炉下部狭隣空間8とは蓮通
され、該原子炉下部狭陶空間8にはその放射方向に円周
上に隣り合うソールプレート11,11間に配置させて
換気管12が複数本配列されており、貫通孔たる各換気
管12の管路を介して前記原子炉下部狭隅空間8と、生
体遮蔽壁14および原子炉1間に形成されている原子炉
脚部アニュラス空間13とが蓮通されている。The lower reactor space 3 and the lower reactor narrow space 8 are connected to each other, and the lower reactor narrow space 8 has sole plates 11 disposed in the radial direction between circumferentially adjacent sole plates 11. A nuclear reactor in which a plurality of ventilation pipes 12 are arranged, and is formed between the reactor lower narrow corner space 8, the biological shielding wall 14, and the reactor 1 through the passage of each ventilation pipe 12 serving as a through hole. The leg annulus space 13 is connected to the leg annulus space 13.
前記生体遮蔽壁14の上部内面と原子炉1間には排気管
15が円周上に複数本設けられ、また生体遮蔽壁14の
上面には各排気管15に蓮適する排気ダクト16が配列
され、該排気ダクト16は空調ユニットに接続されてい
る。A plurality of exhaust pipes 15 are provided on the circumference between the upper inner surface of the biological shielding wall 14 and the reactor 1, and exhaust ducts 16 suitable for each exhaust pipe 15 are arranged on the upper surface of the biological shielding wall 14. , the exhaust duct 16 is connected to an air conditioning unit.
而して貫通孔たる前記各排気管15の管路を通じて原子
炉側部アニュラス空間13と排気ダクト16とが達通さ
れている。前述構成の本発明冷却装置では、給気ダクト
5を通じて冷気が送給され、該給気ダクト5の空気吐出
口10,10′からべデスタル2′の下部および側部に
向って冷気が吹き込まれ、その冷気により原子炉支持コ
ンクリート2が冷却される。The reactor side annulus space 13 and the exhaust duct 16 communicate through the passages of the exhaust pipes 15, which are through holes. In the cooling device of the present invention configured as described above, cold air is supplied through the air supply duct 5, and the cold air is blown from the air discharge ports 10, 10' of the air supply duct 5 toward the lower part and side of the vedestal 2'. The reactor support concrete 2 is cooled by the cold air.
前記原子炉支持コンクリート2を冷却して昇温された空
気はべデスタル2′上面のソールプレート11間に設け
られた換気管12を通って原子炉側部アニュラス空間1
3に流入し、生体遮蔽壁14を冷却しながら原子炉側部
アニュラス空間13を上昇した空気は排気管15を経て
、排気ダクト16に入り、空調ユニットへ送られる。す
なわち、原子炉下部空間3内の昇温された空気は自然対
流により、原子炉下部狭晦空間8、換気管12、原子炉
側部アニユラス空間13、排気管15および排気ダクト
16にスムーズに流れ、かつ空調ユニットに還戻される
。The air heated by cooling the reactor support concrete 2 passes through the ventilation pipe 12 provided between the sole plates 11 on the upper surface of the bedstone 2' and into the reactor side annulus space 1.
The air that flows into the reactor side annulus space 13 while cooling the biological shielding wall 14 passes through the exhaust pipe 15, enters the exhaust duct 16, and is sent to the air conditioning unit. That is, the heated air in the lower reactor space 3 flows smoothly into the lower reactor narrow space 8, the ventilation pipe 12, the reactor side annulus space 13, the exhaust pipe 15, and the exhaust duct 16 due to natural convection. , and returned to the air conditioning unit.
実施例によれば、ソールプレート11,11の間に換気
管12が設けられているので、原子炉支持構造体の強度
がほとんど低下せず、また生体遮蔽壁14の冷却も可能
である。According to the embodiment, since the ventilation pipe 12 is provided between the sole plates 11, 11, the strength of the reactor support structure is hardly reduced, and the biological shielding wall 14 can also be cooled.
本発明は以上説明した構成、作用のものであって、原子
炉下部で、昇溢された空気が、原子炉支持構造体に設け
られた貫通孔を通って、自然対流により原子炉側部また
は上部空間へ移行可能であるため、原子炉下部に高温空
気が滞留して原子炉支持構造体が高温になる障害を完全
に防止しうる効果を有する外、原子炉支持構造体の冷却
装置を簡素化しうる効果がある。The present invention has the configuration and operation described above, and the overflowing air in the lower part of the reactor passes through the through hole provided in the reactor support structure and is caused by natural convection to pass through the reactor side or Since it can be moved to the upper space, it has the effect of completely preventing the problem of high temperature air staying in the lower part of the reactor and causing the reactor support structure to reach high temperatures, and also simplifies the cooling system for the reactor support structure. It has a potential effect.
第1図は従来の原子炉支持構造体の冷却装置を示す縦断
面図、第2図は本発明を下方支持縦暦圧力管型原子炉支
持構造体に適用した場合の一実施例を示す縦断面図、第
3図は第2図のA−A線横断面図である。
1・・・・・・原子炉、2……原子炉支持コンクリート
、2′・・・…同べデスタル、3・・・・・・原子炉下
部空間、5・・・・・・給気ダクト、8・・・・・・原
子炉下部狭隣空間、12・・・・・・換気管、13・・
・・・・原子炉側部アニュラス空間、15…・・・排気
管、16・・・・・・排気ダクト。
茅ー図
茅3図
券2のFIG. 1 is a vertical cross-sectional view showing a conventional cooling device for a nuclear reactor support structure, and FIG. 2 is a vertical cross-sectional view showing an embodiment in which the present invention is applied to a downwardly supported longitudinal pressure tube type reactor support structure. 3 is a cross-sectional view taken along the line A--A in FIG. 2. 1... Nuclear reactor, 2... Reactor support concrete, 2'... Same bed tower, 3... Nuclear reactor lower space, 5... Air supply duct , 8... Narrow space below the reactor, 12... Ventilation pipe, 13...
...Reactor side annulus space, 15...Exhaust pipe, 16...Exhaust duct. Kaya-zu Kaya 3-zu ticket 2
Claims (1)
原子炉の周囲を取囲んでいる原子炉支持構造体の冷却装
置において、前記原子炉支持構造体内で前記原子炉より
下方の下部空間に冷却ガスを供給する手段と、前記原子
炉と前記原子炉支持構造体との間の環状空間と前記下部
空間とを連結し、しかも前記原子炉支持構造体に設けら
れた連絡通路と、前記環状空間に連通している排気管路
とを有したことを特徴する原子炉支持構造体の冷却装置
。1. In a cooling device for a reactor support structure that has a protrusion that supports the lower part of the reactor and surrounds the reactor, a lower space below the reactor within the reactor support structure. means for supplying cooling gas to the reactor; a communication passage provided in the reactor support structure that connects the annular space between the reactor and the reactor support structure and the lower space; 1. A cooling device for a nuclear reactor support structure, comprising an exhaust pipe communicating with an annular space.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP54123874A JPS6027395B2 (en) | 1979-09-28 | 1979-09-28 | Reactor support structure cooling system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP54123874A JPS6027395B2 (en) | 1979-09-28 | 1979-09-28 | Reactor support structure cooling system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5647789A JPS5647789A (en) | 1981-04-30 |
| JPS6027395B2 true JPS6027395B2 (en) | 1985-06-28 |
Family
ID=14871504
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP54123874A Expired JPS6027395B2 (en) | 1979-09-28 | 1979-09-28 | Reactor support structure cooling system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6027395B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6040990A (en) * | 1983-08-17 | 1985-03-04 | 株式会社日立製作所 | Cooling structure of support concrete |
-
1979
- 1979-09-28 JP JP54123874A patent/JPS6027395B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5647789A (en) | 1981-04-30 |
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