JPS5920897A - Device for inspecting inside of reactor container - Google Patents
Device for inspecting inside of reactor containerInfo
- Publication number
- JPS5920897A JPS5920897A JP57130365A JP13036582A JPS5920897A JP S5920897 A JPS5920897 A JP S5920897A JP 57130365 A JP57130365 A JP 57130365A JP 13036582 A JP13036582 A JP 13036582A JP S5920897 A JPS5920897 A JP S5920897A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor containment
- mobile station
- signal transmission
- 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
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
- Monitoring And Testing Of Nuclear Reactors (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、原子炉格納容器内の現場機器などを監視する
格納容器内点検装置の冷却方式に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a cooling system for a containment vessel inspection device that monitors on-site equipment and the like within a nuclear reactor containment vessel.
従来考えられている移動ステーションの搭載機器冷却方
法は、自然空冷、ファンによる強制空付、或いはペルチ
ェ効果による成子冷却が主体である。Conventionally considered methods for cooling equipment mounted on a mobile station are mainly natural air cooling, forced air cooling using a fan, or Nariko cooling using the Peltier effect.
しかし、これらの冷却方式には冷却能力に限界があると
共に、最も冷却能力のある電子冷却方式にあっても点検
装置の発熱量増加に比例した電子冷却器の追設は、冷却
用電源容量の増ｇ′化に招いており、電源部の大型・重
量化をもたらし、点検装置が大型化してしまうという欠
点があった。However, these cooling methods have a limit in their cooling capacity, and even with the electronic cooling method, which has the highest cooling capacity, the addition of an electronic cooler is proportional to the increase in heat generation of the inspection equipment, and the cooling power supply capacity is limited. This leads to an increase in g', which leads to an increase in the size and weight of the power supply section, which has the drawback of increasing the size of the inspection device.
本発明は、このような事情に鑑みてなされたものであり
、その目的とするところは、原子カプラントの重大事故
時のような肯温下においても、監視点検をｉ５Ｔ能とす
る原子炉格納容器内点検装置を提供することにある。The present invention has been made in view of the above circumstances, and its purpose is to provide a reactor containment vessel capable of performing i5T monitoring and inspection even under positive temperature conditions such as in the case of a serious nuclear couplant accident. The purpose of the present invention is to provide an internal inspection device.
本発明の特徴は、原子炉格納容器内に移動ステーション
に加えて、コンプレッサーと熱交換器とを設け、原子炉
格納容器内に充填されている不活性ガス全冷媒として用
いることによって上記の欠点を解消するものである。The feature of the present invention is to provide a compressor and a heat exchanger in addition to a mobile station in the reactor containment vessel, and to use the inert gas filled in the reactor containment vessel as the entire refrigerant, thereby solving the above drawbacks. It is something that will be resolved.
第１図に本発明の一実施例を示す、移動ステー７ヨ／は
ＴＶ車ｌと、コントロール車４よυ構成されている。コ
ントロール車４内には種々の制御回路、通信部、及び′
電源部が内蔵されている。FIG. 1 shows an embodiment of the present invention. A mobile station 7/ is composed of a TV car 1 and a control car 4. Inside the control vehicle 4, there are various control circuits, communication sections, and
It has a built-in power supply.
冷却設備は熱交換器２２、コンプレッサ２３及び冷媒輸
送チューブ２０より構成される。冷却方法を以下に説明
する。The cooling equipment includes a heat exchanger 22, a compressor 23, and a refrigerant transport tube 20. The cooling method will be explained below.
原子炉格納容器内に設備された熱交換器２２に、吸気口
２８より取込まれたＮ２ガス２９は、吸水管２５より取
込まれたポンプ冷却水（例えば沸騰水型原子炉では原子
炉再循環ボング）にて冷却され、コンプレッサ２３によ
って圧縮冷媒となり冷媒輸送チューブ２０を通ってコン
トロール車内に吹き付けられる。また、ＴＶ車１とコン
トロール車４も冷媒輸送チューブ２０にて連絡されてい
るため、コントロール車４内に送出される冷媒はＴＶ車
車内内も吹き付けられ、それぞれの内部にある発熱機器
を所要温度に冷却する。この様にし又吹き付けられた冷
媒（Ｎ２ガス）は、排気口２７より格納容器内に拡散さ
れる。The N2 gas 29 taken in from the intake port 28 to the heat exchanger 22 installed in the reactor containment vessel is supplied to the pump cooling water taken in from the water intake pipe 25 (for example, in a boiling water reactor, the reactor The refrigerant is compressed by the compressor 23 and sprayed into the control vehicle through the refrigerant transport tube 20. Furthermore, since the TV car 1 and the control car 4 are also connected through the refrigerant transport tube 20, the refrigerant sent into the control car 4 is also sprayed inside the TV car, heating the heat generating equipment inside each to the required temperature. Cool to The refrigerant (N2 gas) sprayed in this manner is diffused into the containment vessel through the exhaust port 27.
第２図は、本発明の一実施例を示す機能ブロック図であ
る。FIG. 2 is a functional block diagram showing one embodiment of the present invention.
熱交換器２２に取込まれてポンプ冷却水２５によって一
次冷却されたＮ、ガス２９ケよ、コンプレッサ２３によ
り昇圧され一部が液化冷却された冷媒４５となり、バル
ブ３９を通ってコントロール車４及びＴＶ車車内内送出
される。装置の冷却に使用されて加熱された昇温ガス３
５は、移動スデーション外部へ拡散する。冷媒としては
、原子炉格納容器内雰囲気ガスであるため格納容器内へ
排出しても影響のｌいＮ、ガスを用いる。また過冷却を
避けるためにＴＶ車ｌとコントロール車４内に、サーモ
スタット３０を設ける。サーモスタット３０にて検出さ
れた温度信号３４ば、車内温度検出回路３２に送られる
。温度制御１ａ号３６を受けてパルプ制飢回路３７が働
き、パルプ開度信号３８が送出され、パルプ３９の開度
が調節される。The nitrogen gas 29 taken into the heat exchanger 22 and primarily cooled by the pump cooling water 25 is pressurized by the compressor 23 and becomes the refrigerant 45, which is partially liquefied and cooled, and passes through the valve 39 to the control vehicle 4 and The TV is broadcast inside the car. Heated heated gas used to cool the device 3
5 diffuses outside the mobile station. As the refrigerant, 1N gas is used, which is an atmospheric gas within the reactor containment vessel and therefore has no effect even if discharged into the containment vessel. Furthermore, a thermostat 30 is installed in the TV car 1 and the control car 4 to avoid overcooling. A temperature signal 34 detected by the thermostat 30 is sent to an in-vehicle temperature detection circuit 32. The pulp starvation circuit 37 operates in response to the temperature control number 1a 36, a pulp opening degree signal 38 is sent out, and the opening degree of the pulp 39 is adjusted.
その結果、冷媒４５の吐出着が制御され、車内温度が適
度に保たれる。ｌお４１は各部に電力を供給するための
電源である。As a result, the discharge and deposition of the refrigerant 45 is controlled, and the temperature inside the vehicle is maintained at an appropriate level. Reference numeral 41 is a power source for supplying power to each part.
以上の様に本発明によれば、従米不５Ｔ能と考えられて
いた原子カプラントの重大事故発生時にも原子炉格納容
器内の尚温壇境下での監視点検がＢ■能となり、Ｉ！／
１」えば原子炉冷却材喪失事故発生時の超高温πにおい
ても原子炉格納表器内状態の的確な把握がＯＴ化となり
、原子力発電所の安全性・信穣性を大幅に向上すること
ができる。As described above, according to the present invention, even in the event of a serious accident in a nuclear couplant, which was thought to be ineffective, monitoring and inspection under the hot stage inside the reactor containment vessel becomes B■ capability, and I! /
1. For example, even at extremely high temperatures of π when a loss of reactor coolant accident occurs, OT can accurately grasp the state inside the reactor containment, greatly improving the safety and reliability of nuclear power plants. can.
第１区は、本発明の一実施例のシステム外観図、第２図
は同じく機能ブロック図である。
ｌ・・・ＴＶＩＬ、４・・・コントロール車、５・・・
走行）Ｌ’ −ト、６・・・通信用漏洩同軸ケーブル、
７・・・電力供給用トロリーバー、２０・・・冷媒輸送
チューブ、２１・・・ケーブルリール、２３・・・コン
プレソ？、２２・・・熱交換器。The first section is a system external view of an embodiment of the present invention, and FIG. 2 is a functional block diagram. l...TVIL, 4...control vehicle, 5...
Running) L'-t, 6...Leaky coaxial cable for communication,
7... Trolley bar for power supply, 20... Refrigerant transport tube, 21... Cable reel, 23... Compresso? , 22... heat exchanger.
Claims (1)
し、原子力発電所の格納容器内を移動して格納容器内の
計測を行なう移動ステージョンと、信号伝送路と、信号
伝送装置と、表示器とを有し、上記信号伝送路を介して
送られる上記検出器から得られた・清報を信号伝送装置
で受信して、上記表示器に表示い原子炉格納容器外に設
置される監視制御盤とから構成される原子炉格納容器内
自動点検装置において、原子炉格納容器内にコンブレノ
ザーと、熱交換器と、コンプレッサーと上記移動ステー
ション金つなぐ冷媒輸送路とを設け、上６己熱交換器に
て原子炉格納容器内雰囲気ガスを原子炉格納容器内機器
冷却水と熱交換して冷却した後、上記コンプレッサーで
圧縮し、上記冷媒桶送路を介して移動ステーションへ圧
縮ガスを送り、移動ステーションの冷却を行うこと全特
徴とする原子炉格納容器内点検装置。1. A mobile station equipped with at least one detector and a signal transmission device, which moves within a containment vessel of a nuclear power plant to perform measurements inside the containment vessel, a signal transmission path, and a signal transmission device; installed outside the reactor containment vessel. In the automatic inspection system inside the reactor containment vessel, which consists of a monitoring and control panel, a combination nozzer, a heat exchanger, and a refrigerant transport path connecting the compressor and the above-mentioned mobile station are installed inside the reactor containment vessel. After the atmospheric gas inside the reactor containment vessel is cooled by heat exchange with the equipment cooling water inside the reactor containment vessel in the exchanger, it is compressed in the above compressor, and the compressed gas is sent to the mobile station via the above refrigerant pipe passage. A nuclear reactor containment vessel interior inspection device, which is characterized by cooling a mobile station.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57130365A JPS5920897A (en) | 1982-07-28 | 1982-07-28 | Device for inspecting inside of reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57130365A JPS5920897A (en) | 1982-07-28 | 1982-07-28 | Device for inspecting inside of reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5920897A true JPS5920897A (en) | 1984-02-02 |
Family
ID=15032627
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57130365A Pending JPS5920897A (en) | 1982-07-28 | 1982-07-28 | Device for inspecting inside of reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5920897A (en) |
-
1982
- 1982-07-28 JP JP57130365A patent/JPS5920897A/en active Pending
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