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JPS6058435B2 - Cooling method and device inside the reactor containment vessel - Google Patents
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JPS6058435B2 - Cooling method and device inside the reactor containment vessel - Google Patents

Cooling method and device inside the reactor containment vessel

Info

Publication number
JPS6058435B2
JPS6058435B2 JP52041108A JP4110877A JPS6058435B2 JP S6058435 B2 JPS6058435 B2 JP S6058435B2 JP 52041108 A JP52041108 A JP 52041108A JP 4110877 A JP4110877 A JP 4110877A JP S6058435 B2 JPS6058435 B2 JP S6058435B2
Authority
JP
Japan
Prior art keywords
containment vessel
reactor containment
inert gas
liquid inert
liquid
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
Application number
JP52041108A
Other languages
Japanese (ja)
Other versions
JPS53131387A (en
Inventor
俊彦 山崎
国雄 西山
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.)
Hitachi Ltd
Original Assignee
Hitachi Plant Engineering and Construction Co 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 Hitachi Plant Engineering and Construction Co Ltd filed Critical Hitachi Plant Engineering and Construction Co Ltd
Priority to JP52041108A priority Critical patent/JPS6058435B2/en
Publication of JPS53131387A publication Critical patent/JPS53131387A/en
Publication of JPS6058435B2 publication Critical patent/JPS6058435B2/en
Expired 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
    • 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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)

Description

【発明の詳細な説明】 本発明は原子炉格納容器内部の冷却方法およびその装
置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method and apparatus for cooling the inside of a nuclear reactor containment vessel.

一般に、原子炉格納容器(以下PCVという)は、原
子力発電のための心臓部である原子炉、主蒸気管、給水
管、再循環水管、再循環ポンプなど熱源の発生、運搬な
どに供する重要な機材を格納し、さらにこれらの機器か
ら冷却材の漏失などによつて生じる放射線災害から一般
公衆、従業員を防護する重要な機器である。
In general, the reactor containment vessel (hereinafter referred to as PCV) is the core of nuclear power generation, which is the core of the nuclear reactor, main steam pipes, water supply pipes, recirculation water pipes, recirculation pumps, and other important components used to generate and transport heat sources. It is an important device for storing equipment and protecting the general public and employees from radiation hazards caused by leakage of coolant from these equipment.

このPCV内部は原子炉を運転することによつて原子炉
、配管類の保温材からの熱通過によつて内部雰囲気温度
は上昇する。この雰囲気温度が上昇すると原子炉などの
重要な機器を制御している電気制御機器に支障をきたし
、延いては原子炉の信頼性、安全性に悪影響をおよぼす
。このためこのPCV内部の雰囲気温度を規定値以下に
おさえるようPCV内部に冷却装置を設置し冷却してい
る。この冷却方法としては、一般に、PCV内部に気一
液熱交換器を設置し、この熱交換器により冷却された気
体をダクトを介して送風機によつてPC■内部に拡散さ
せて冷却する方法が採用されている。ところで、原子力
発電所では、原子炉本体およびPCV内制御機器の保守
のために定期点検作業を行なつているが作業者の被曝を
防止するために作業スペースの拡大および作業の簡素化
が図られている。
When the nuclear reactor is operated, the temperature of the internal atmosphere inside the PCV rises due to the passage of heat from the heat insulating material of the reactor and piping. When this atmospheric temperature rises, it causes trouble to the electrical control equipment that controls important equipment such as the nuclear reactor, and has a negative impact on the reliability and safety of the nuclear reactor. For this reason, a cooling device is installed inside the PCV to cool the inside of the PCV so as to keep the atmospheric temperature inside the PCV below a specified value. Generally speaking, this cooling method is to install a gas-liquid heat exchanger inside the PCV and diffuse the gas cooled by this heat exchanger through a duct into the inside of the PC using a blower. It has been adopted. By the way, at nuclear power plants, periodic inspection work is carried out to maintain the reactor main body and control equipment in the PCV, but in order to prevent workers from being exposed to radiation, efforts are being made to expand the work space and simplify the work. ing.

しかし、従来の送風機、気一液熱交換器、ダクト等を組
合せた冷却設備では、その占有体積がPC■内部容績の
約6%にも達し、その小型化が要望されている。本発明
の目的は、簡単な装置により安価かつ少ない占有体積て
PC■内部の雰囲気温度を規定温度以下に下げることが
できるとともに、定期点検作業時のスペースの拡大を図
り、作業者の被曝を防止することができる原子炉格納容
器内部の冷却方法およびその装置を堤供することである
However, conventional cooling equipment that combines a blower, a gas-to-liquid heat exchanger, a duct, etc. occupies approximately 6% of the internal capacity of a PC, and there is a demand for its miniaturization. The purpose of the present invention is to use a simple device to lower the ambient temperature inside a PC to a specified temperature or lower using a low-cost and small-occupancy device, as well as to expand the space available for periodic inspections and prevent workers from being exposed to radiation. The objective is to provide a method and device for cooling the inside of a nuclear reactor containment vessel.

本発明は、液化された不活性ガスをPCV内に散布し、
その気化熱によりPCV内部を冷却するようにして前記
目的を達成しようとするものである。以下、本発明の一
実施例を図面を参照してより詳細に説明する。
The present invention sprays liquefied inert gas into the PCV,
The purpose is to achieve the above object by cooling the inside of the PCV using the heat of vaporization. Hereinafter, one embodiment of the present invention will be described in more detail with reference to the drawings.

外周をコンクリートで覆い、さらに鉄筋コンクリート建
屋内に設置された原子炉格納容器(PCV)1は、内部
に発熱源てある原子炉2を収納し、この原子炉2の周囲
には放射線遮蔽壁3が.設けられている。
A reactor containment vessel (PCV) 1 whose outer periphery is covered with concrete and is further installed in a reinforced concrete building houses a nuclear reactor 2 with a heat source inside, and a radiation shielding wall 3 is placed around this reactor 2. .. It is provided.

前記PCVl内の放射線遮蔽壁3の外側には、液体不活
性ガスとしての液体窒素をPCVl内に散布するための
散布手段としてスプレーノズル4が複数個配設されてい
る。
A plurality of spray nozzles 4 are disposed outside the radiation shielding wall 3 inside the PCVl as a spraying means for spraying liquid nitrogen as a liquid inert gas into the PCVl.

これらのスプレーノズ.ル4は、途中に流量制御弁5を
有する配管6を介してPCVlの底部に設けられた液体
窒素の供給手段としての液体窒素貯蔵器7に接続されて
いる。この液体窒素貯蔵器7は、液体窒素圧送用ポンプ
および貯蔵タンクを有するとともに、該貯蔵,器7の側
方に設置された回収液化手段としての窒素液化装置8に
接続されている。前記PC■1内の所要位置、すなわち
、PC■1内部の発熱源によるPC■1の内部雰囲気温
度の上昇を測定するに好都合な複数個所にに温度検出器
9が設けられている。
These spray nozzles. The pipe 4 is connected via a pipe 6 having a flow control valve 5 in the middle to a liquid nitrogen storage device 7 provided at the bottom of the PCVl as a liquid nitrogen supply means. This liquid nitrogen storage device 7 has a pump for pumping liquid nitrogen and a storage tank, and is connected to a nitrogen liquefaction device 8 as a recovery and liquefaction means installed on the side of the storage device 7. Temperature detectors 9 are provided at predetermined positions within the PC 1, that is, at a plurality of locations convenient for measuring the rise in the temperature of the internal atmosphere of the PC 1 due to heat sources inside the PC 1.

この温度検出器9からの信号は、前記流量制御弁5に連
設され、該制御弁5の流量を制御する温度制御器10に
伝達されるように構成されている。このような構成にお
いて、液体窒素貯蔵器7から送られる液体窒素は、配管
6を介してPC■1内部の適当な高さ、場所に設けられ
たスプレーノズル4からPCVl内に散布される。
A signal from the temperature detector 9 is connected to the flow control valve 5 and is configured to be transmitted to a temperature controller 10 that controls the flow rate of the control valve 5. In such a configuration, liquid nitrogen sent from the liquid nitrogen storage device 7 is sprayed into the PCVl through the pipe 6 from the spray nozzle 4 provided at an appropriate height and location inside the PC1.

この散布さaれた液体窒素は蒸発することによつてPC
■1内の雰囲気より蒸発潜熱を吸収してPC■1内部雰
囲気温度を下ける。この気化した窒素は、膨張機などか
らなる窒素液化装置8により液化され、再び液体窒素貯
蔵器7に貯蔵され、再度前述の順路で循環することにな
る。前記液体窒素の散布量は、PC■1の内部の随所に
設置された温度検出器9によつて検出されるPCVl内
部雰囲気温度に基づいて温度制御器10が作動され、こ
れにより流量制御弁5が作動されて制御される。
This sprayed liquid nitrogen evaporates and becomes PC.
(2) Absorbs the latent heat of vaporization from the atmosphere inside PC (1) to lower the temperature of the internal atmosphere of PC (1). This vaporized nitrogen is liquefied by a nitrogen liquefaction device 8 consisting of an expander and the like, stored again in the liquid nitrogen storage device 7, and circulated again in the above-described route. The amount of liquid nitrogen to be sprayed is determined by operating the temperature controller 10 based on the temperature of the internal atmosphere of the PCV1 detected by temperature detectors 9 installed at various locations inside the PC1. is activated and controlled.

この散布量の制御により、PCVl内部雰囲気温度が規
定温度に保たれることとなる。なお、実施にあたり、液
化される不活性ガスとしては窒素ガスに限らずアルゴン
ガスなどの他の不活性ガスでもよいが、窒素ガスとすれ
ば、通常PCVl内には制御機器等の爆発を避けるため
に窒素ガスが充填されており、これをそのまま利用でき
て経済上有利である。
By controlling the amount of spraying, the temperature of the PCVl internal atmosphere is maintained at a specified temperature. In carrying out the process, the inert gas to be liquefied is not limited to nitrogen gas, but other inert gases such as argon gas may be used, but if nitrogen gas is used, it is usually necessary to avoid explosion of control equipment etc. inside the PCVl. is filled with nitrogen gas, which is economically advantageous because it can be used as is.

また、液体不活性ガスの回収液化手段(窒素液化装置6
)の本体および液体不活性ガスの供給手段(液体窒素貯
蔵器7)は、必らずしもPCVlの内部に設ける必要は
ないが、内部に設ければ、放射能を帯びた冷却材の漏出
時等に、その対策がとり易いという利点がある。さらに
、散布手段としては、スプレーノズル4を用いるが好ま
しいが、必ずしもこれに限らず単に滴下するようにして
もよく、あるいは布、焼結金属等の多孔質の物質から蒸
発させるようにしてもよい。上述のように、本発明によ
れば、従来の送風機、気一液熱交換器、ダクト等を組合
せた冷却装置よりもPCV内の占有体積が小さく、定期
点検時の作業スペースが拡大し、作業者の安全を維持で
きるという効果がある。
In addition, a liquid inert gas recovery and liquefaction means (nitrogen liquefaction device 6
) and the liquid inert gas supply means (liquid nitrogen storage 7) do not necessarily have to be installed inside the PCVl, but if they are installed inside, leakage of radioactive coolant can be avoided. This has the advantage that countermeasures can be easily taken at any time. Further, as the spraying means, it is preferable to use the spray nozzle 4, but the invention is not limited thereto, and it may be simply dripping, or it may be evaporated from a porous substance such as cloth or sintered metal. . As described above, according to the present invention, the volume occupied within the PCV is smaller than that of a conventional cooling system that combines a blower, a gas-liquid heat exchanger, a duct, etc., and the work space during periodic inspections is expanded, making it easier to carry out work. This has the effect of maintaining the safety of people.

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

図は、本発明に係る冷却装置の一実施例を収納した原子
炉格納容器の概略断面図である。 1・・・・・・原子炉格納容器、2・・・・・・原子炉
、4・・・・・散布手段としてのスプレーノズル、5・
・・・・・流量制御弁、6・・・・・・配管、7・・・
・・・供給手段としての液体窒素貯蔵器、8・・・・・
・回収液化手段としての窒素液化装置、9・・・・・・
温度検出器、10・・・・・温度制御器。
The figure is a schematic cross-sectional view of a reactor containment vessel housing an embodiment of a cooling device according to the present invention. 1... Reactor containment vessel, 2... Nuclear reactor, 4... Spray nozzle as a spraying means, 5...
...Flow control valve, 6...Piping, 7...
...Liquid nitrogen storage as a supply means, 8...
・Nitrogen liquefaction device as recovery liquefaction means, 9...
Temperature detector, 10...Temperature controller.

Claims (1)

【特許請求の範囲】 1 原子炉格納容器内に設けられた温度検出器の検出値
をもとに制御しつつ、該原子炉格納容器内に液体状の不
活性ガスを散布し、これによつて原子炉格納容器内の温
度を原子炉格納容器内の収納制御機器の保護に最も適し
た温度に保つことを特徴とする原子炉格納容器内部の冷
却方法。 2 前記特許請求の範囲第1項に記載の原子炉格納容器
内部の冷却方法において、前記液体不活性ガスは液体窒
素であることを特徴とする原子炉格納容器内部の冷却方
法。 3 原子炉格納容器内の所要位置に設けられた液体不活
性ガス散布手段と、この液体不活性ガス散布手段に液体
不活性ガスを供給する供給手段と、前記原子炉格納容器
内に散布され気化した不活性ガスを回収し液化する回収
液化手段と、前記液体不活性ガス散布手段と供給手段と
を液体不活性ガス流量制御弁を介して接続する配管と、
前記原子炉格納容器内の所要箇所に設置された温度検出
器と、この温度検出器からの検出値により前記液体不活
性ガス制御弁を高温時に開放する方向に制御する温度制
御器とを備えたことを特徴とする原子炉格納容器内部の
冷却装置。 4 前記特許請求の範囲第3項に記載の原子炉格納容器
内部の冷却装置において、前記液体不活性ガスの供給手
段および液体不活性ガスの回収液化手段は、原子炉格納
容器内に設けられていることを特徴とする原子炉格納容
器内部の冷却装置。 5 前記特許請求の範囲第3項または第4項に記載の原
子炉格納容器内部の冷却装置において、前記液体不活性
ガス散布手段はスプレーノズルであることを特徴とする
原子炉格納容器内部の冷却装置。 6 前記特許請求の範囲第3項ないし第5項のいずれか
に記載の原子炉格納容器内部の冷却装置において、前記
液体不活性ガスは液体窒素であることを特徴とする原子
炉格納容器内部の冷却装置。
[Claims] 1. Spraying liquid inert gas into the reactor containment vessel while controlling based on the detected value of a temperature detector installed in the reactor containment vessel. A method for cooling the inside of a reactor containment vessel, characterized in that the temperature inside the reactor containment vessel is maintained at a temperature most suitable for protecting control equipment contained within the reactor containment vessel. 2. The method for cooling the inside of a nuclear reactor containment vessel according to claim 1, wherein the liquid inert gas is liquid nitrogen. 3. A liquid inert gas dispersion means provided at a predetermined position within the reactor containment vessel, a supply means for supplying liquid inert gas to the liquid inert gas dispersion means, and a liquid inert gas dispersion means disposed within the reactor containment vessel and vaporized. a recovery liquefaction means for recovering and liquefying the inert gas; and piping connecting the liquid inert gas distribution means and the supply means via a liquid inert gas flow rate control valve;
The reactor containment vessel includes a temperature detector installed at a predetermined location, and a temperature controller that controls the liquid inert gas control valve to open at high temperature based on the detected value from the temperature detector. A cooling device inside a nuclear reactor containment vessel, characterized by: 4. In the cooling device inside the reactor containment vessel according to claim 3, the liquid inert gas supply means and the liquid inert gas recovery and liquefaction means are provided within the reactor containment vessel. A cooling device inside a nuclear reactor containment vessel, characterized by: 5. The cooling device for the inside of the reactor containment vessel according to claim 3 or 4, wherein the liquid inert gas distribution means is a spray nozzle. Device. 6. The cooling device for the inside of the reactor containment vessel according to any one of claims 3 to 5, wherein the liquid inert gas is liquid nitrogen. Cooling system.
JP52041108A 1977-04-11 1977-04-11 Cooling method and device inside the reactor containment vessel Expired JPS6058435B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP52041108A JPS6058435B2 (en) 1977-04-11 1977-04-11 Cooling method and device inside the reactor containment vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52041108A JPS6058435B2 (en) 1977-04-11 1977-04-11 Cooling method and device inside the reactor containment vessel

Publications (2)

Publication Number Publication Date
JPS53131387A JPS53131387A (en) 1978-11-16
JPS6058435B2 true JPS6058435B2 (en) 1985-12-19

Family

ID=12599269

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52041108A Expired JPS6058435B2 (en) 1977-04-11 1977-04-11 Cooling method and device inside the reactor containment vessel

Country Status (1)

Country Link
JP (1) JPS6058435B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5529797B2 (en) * 2011-04-20 2014-06-25 網矢 ハル子 Reactor cooling system
JP2017020998A (en) * 2015-07-10 2017-01-26 元浩 岡田 Nuclear power plant.

Also Published As

Publication number Publication date
JPS53131387A (en) 1978-11-16

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