JPS5946593A - Sodium equipment surrounding construction for fast breeder - Google Patents

Sodium equipment surrounding construction for fast breeder

Info

Publication number
JPS5946593A
JPS5946593A JP57157295A JP15729582A JPS5946593A JP S5946593 A JPS5946593 A JP S5946593A JP 57157295 A JP57157295 A JP 57157295A JP 15729582 A JP15729582 A JP 15729582A JP S5946593 A JPS5946593 A JP S5946593A
Authority
JP
Japan
Prior art keywords
sodium
vessel
concrete
fast breeder
guard
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
JP57157295A
Other languages
Japanese (ja)
Inventor
修 楮
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP57157295A priority Critical patent/JPS5946593A/en
Publication of JPS5946593A publication Critical patent/JPS5946593A/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

  • Secondary Cells (AREA)
  • Other Liquid Machine Or Engine Such As Wave Power Use (AREA)
  • Revetment (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】 本発明は高速増殖炉におけるナトリウム機器のガードベ
ッセルを廃止し、熱的防護策を講じた建家及び構築物に
てその機能を代替し、更に雰囲気を高温に保つことによ
ってナトリウム機器およびその配管を裸にして設計・検
査等を容易にする、高速増殖炉のナトリウム機器周辺構
築物に関する。
[Detailed Description of the Invention] The present invention eliminates guard vessels for sodium equipment in fast breeder reactors, replaces their functions with buildings and structures that take thermal protection measures, and further maintains the atmosphere at a high temperature. This invention relates to structures surrounding sodium equipment in fast breeder reactors that expose sodium equipment and its piping to facilitate design and inspection.

従来、液体金属冷却高速増殖炉の高温機器廻り構造とし
て原子炉容器、及びその周辺は第1図に示すようになっ
ている。
Conventionally, the structure around the high-temperature equipment of a liquid metal cooled fast breeder reactor, including the reactor vessel and its surroundings, is as shown in FIG.

図において、1は原子炉容器、2は原子炉容器1からの
ナトリウム漏洩時にす) IJウムを貯留し、システム
の液面保持を確保するためのガードベッセルである。3
は、原子炉容器1とガードベッセル2の耐震振れ止めで
、埋込金物5にて床コンクIJ−)14に固定された支
持構造物4にて、地震時の原子炉容器1、ガードベッセ
ル2の変位を拘束するように構成されている。
In the figure, 1 is a reactor vessel, and 2 is a guard vessel for storing IJium (in case of sodium leakage from the reactor vessel 1) and ensuring that the liquid level of the system is maintained. 3
is an earthquake-resistant steady rest for the reactor vessel 1 and the guard vessel 2, and the support structure 4 fixed to the floor concrete IJ-) 14 with the embedded metal fittings 5 is used to secure the reactor vessel 1 and the guard vessel 2 during an earthquake. It is configured to restrain the displacement of.

また、図において6はガードベッセル2の胴で、7はガ
ードベッセル2の自重、地震力を受けるためのスカート
部であり、被デスタル10上に据えられたソールプレー
ト9に7ランノ部8で固定されている。11,12は鋼
板で、その円部にはそれぞれコンクリート13.14が
充填されている。
In addition, in the figure, 6 is the body of the guard vessel 2, and 7 is a skirt part for receiving the own weight and seismic force of the guard vessel 2, and is fixed to the sole plate 9 placed on the destabilized object 10 by the 7 run part 8. has been done. Reference numerals 11 and 12 are steel plates, and their circular parts are filled with concrete 13 and 14, respectively.

さらに、16は炉容器室雰囲気で、通常は壁コンクリー
トの保護のために雰囲気冷却がなされている。
Further, reference numeral 16 denotes the atmosphere of the furnace vessel chamber, which is normally cooled to protect the wall concrete.

上記構造において、機器からの放熱を防止するためにガ
ードベッセル2には断熱材15が設けられており、ガー
ドベッセル2と原子炉容器lとの環状部から高温ガスが
室内に漏れ出ることを防止するために、ガードベッセル
2の頂部にはシール構造17が設置されている。
In the above structure, the guard vessel 2 is provided with a heat insulating material 15 to prevent heat radiation from the equipment, and prevents high-temperature gas from leaking into the room from the annular portion between the guard vessel 2 and the reactor vessel l. In order to do this, a seal structure 17 is installed on the top of the guard vessel 2.

し力)るに、上述した従来の構造では、■ガードベッセ
ル2の支持のためにスカート部7.7ランジ部8、ソー
ルプレート9及びペデスタル10等の構造が必要となる
こと、■耐震振れ止め3が二重の複雑な構造となること
、■原子炉容器lの熱形き工うからコンタリートを防護
するために雰囲気冷却が必要であること、■ガードベッ
セル2から漏れ出るナトリウムが炉容器室雰囲気16の
室内でスプレィ火災やプール火災を発生するときの対策
が必要であること、等の不利さがあり、設計上の難度が
高く、物量が多く、LX))も据付けに要する工期が長
くなるものであり、空調負荷が大きい等の欠点があった
However, in the conventional structure described above, ■ structures such as the skirt portion 7, 7, lunge portion 8, sole plate 9, and pedestal 10 are required to support the guard vessel 2; ■ earthquake-resistant steady rests; 3 has a double and complex structure; ■Atmosphere cooling is required to protect the contour due to the thermal shaping of the reactor vessel 1; ■Sodium leaking from guard vessel 2 may cause the atmosphere in the reactor vessel chamber. There are disadvantages such as the need to take measures in case a spray fire or pool fire occurs in a room of 16, the design is highly difficult, the amount of material is large, and the construction period required for installation is also long. However, there were drawbacks such as a large air conditioning load.

本発明は上述した従来構造の欠点を解決するためになさ
れたもので、ナトリウム機器に設置するガードベッセル
を廃止し、ナトリウムは周辺の壁、床を利用して部屋内
に貯留し、室内は通常高温のま1として、冷却はコンク
リートを直接冷やす等、熱的防護策を講じた構造であり
、構造は簡素で、信頼性があり、工期が短かく、空調等
に費やされる熱損失の少ない高速増殖炉におけるガード
ベッセル機能を有する構築物を提供せんとするものであ
る。
The present invention was made to solve the above-mentioned drawbacks of the conventional structure, and eliminates the guard vessel installed in the sodium equipment, and stores the sodium in the room using the surrounding walls and floor. As a high-temperature solution, cooling is a structure that takes thermal protection measures such as directly cooling the concrete, and the structure is simple, reliable, short construction period, and high-speed with less heat loss spent on air conditioning. The purpose of this invention is to provide a structure that has a guard vessel function in a breeder reactor.

以下、本発明による実施例を第2図にもとづいて詳細に
説明する。
Hereinafter, embodiments according to the present invention will be described in detail based on FIG. 2.

図において20は原子炉容器で、ガードベッセルを廃止
した構造である。21は下部振れ止め、22.23は鋼
板で内部にはそれぞれコンクリート24.25が充填さ
れて訃り、コンクリート24.25中にはコンクリート
冷却のために冷却管26を埋設し、常時冷却剤を流し、
熱除去を行なうようになっている。
In the figure, 20 is a reactor vessel, which has a structure in which a guard vessel is eliminated. 21 is a lower steady rest, 22 and 23 are steel plates, each of which is filled with concrete 24 and 25. A cooling pipe 26 is buried in the concrete 24 and 25 to cool the concrete, and a coolant is constantly supplied. sink,
It is designed to remove heat.

また、鋼板22.23の表面にはコンクリート24.2
5への熱流入を防止するために断熱材27が設置されて
おり、機器、配管類には断熱材が使用されていない。
In addition, concrete 24.2 is placed on the surface of the steel plate 22.23.
A heat insulating material 27 is installed to prevent heat from flowing into the device 5, and no heat insulating material is used for equipment or piping.

なお、上記原子炉容器20の上部は、図示していない上
端7ランジにて支持されている。
Note that the upper part of the reactor vessel 20 is supported by an upper end 7 flange (not shown).

つぎに、上述した構造における原子炉容器の作用につい
て詳述する。
Next, the operation of the reactor vessel in the above structure will be explained in detail.

高温となるが、断熱材27のために、コンクリート24
.25への熱流出は抑制されるので、コンクリート24
.25を冷却し保護するための冷却管26の除去すべき
熱量は少なくてすむ。
Although the temperature is high, the concrete 24 is heated due to the insulation material 27.
.. Since the heat leakage to 25 is suppressed, concrete 24
.. The amount of heat that must be removed by the cooling pipe 26 for cooling and protecting the cooling tube 25 is small.

がないので、原子炉容器20からの熱放散を助長するこ
となく熱損失が少ない。
Since there is no heat dissipation from the reactor vessel 20, there is less heat loss.

また、冷却管26は、ナトリウムと接触しないから、水
などの冷媒を使用することができ、冷却性能がよくなる
ものであり、系統のコンパクト化が可能になる。
Furthermore, since the cooling pipe 26 does not come into contact with sodium, it is possible to use a refrigerant such as water, which improves the cooling performance and allows the system to be made more compact.

さらに、従来構造のように炉容器室雰囲気28を冷却し
ないので、そのための冷却系統は不要になる。
Furthermore, unlike the conventional structure, the atmosphere 28 in the furnace vessel chamber is not cooled, so a cooling system for that purpose is not required.

5− 一方、ナトリウム漏洩時には、炉容器室雰囲気28の空
間へナトリウムが漏れ出てくるが、炉容器室雰囲気28
の空間容積を制限することにより、システムからの過度
のナトリウムの漏出を防止し液面の維持を行なうことが
可能である。
5- On the other hand, when sodium leaks, sodium leaks into the space of the furnace vessel chamber atmosphere 28;
By limiting the spatial volume of the system, it is possible to prevent excessive sodium leakage from the system and maintain the liquid level.

また、炉容器室雰囲気28の空間でのナトリウムのスゲ
レイ火災、プール火災に対しては、断熱材27のために
コンクリートへの熱流入は緩慢なものとなり、冷却管2
6にて熱除去をすることにより、コンクリート24.2
5、鋼板22.23の温度上昇を防止することができる
とともに、炉容器室雰囲気28の空間に貯まるナトリウ
ムの熱除去が可能で、ナトリウムの漏洩事故後の熱荷重
を早期に沈静することが可能である。
In addition, in the case of a sodium sedge fire or a pool fire in the space of the furnace vessel chamber atmosphere 28, heat inflow into the concrete is slow due to the insulation material 27, and the cooling pipe 2
By removing heat in step 6, concrete 24.2
5. It is possible to prevent the temperature rise of the steel plates 22 and 23, and it is also possible to remove the heat from the sodium accumulated in the space of the furnace vessel chamber atmosphere 28, and it is possible to quickly calm down the thermal load after a sodium leakage accident. It is.

さらに、定検時には、機器、配管が露出しているので、
断熱材を除去したりする必要がすく、供用期間中検査(
ISIJ、補修などが容易に行ない得る。
Furthermore, during regular inspections, equipment and piping are exposed, so
It is less necessary to remove the insulation material, and inspections (
ISIJ, repairs, etc. can be easily performed.

以上詳細に説明したように、不発明による高速増殖炉の
原子炉容器周辺構築物によれば、ガード6− ベッセル、および雰囲気内冷却が不要な構造であり、構
造が簡素化されて、コンノやクトになるものであり、物
量が減少し、工期短縮が期待できる。
As explained in detail above, the uninvented structure around the reactor vessel of a fast breeder reactor has a structure that does not require a guard 6-vessel or cooling in the atmosphere, and the structure is simplified, allowing the container and This means that the amount of materials will be reduced and the construction period can be expected to be shortened.

1K、ナトリウム漏洩時の液位確保が可能であり、コン
クリート、鋼板な熱形きようから防護できる。
1K, it is possible to secure the liquid level in the event of a sodium leak, and it can be protected from hot molds such as concrete and steel plates.

さらに、不発明による構造では、定検、供用期間中検査
等が容易に行なわ扛る等の効果を奏する。
Further, the structure according to the invention has the advantage that periodic inspections, inspections during the service period, etc. can be easily carried out.

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

第1図は従来の実施例を示す原子炉容器、及びその周辺
部の断面図、第2図は本発明による実施例を示す原子炉
容器及びその周辺部の断面図である0 1.20・・・原子炉容器、2・・・ガードベッセル、
15.27・・・断熱材、 16.28・・・炉容器室雰囲気、 21・・・下部振れ止め、22.23・・・鋼板、13
.14.24.25・・・コンクリート、26・・・冷
却管。 7−
Fig. 1 is a sectional view of a reactor vessel and its surrounding area showing a conventional embodiment, and Fig. 2 is a sectional view of a reactor vessel and its surrounding area showing an embodiment according to the present invention. ...Reactor vessel, 2...Guard vessel,
15.27...Insulating material, 16.28...Furnace vessel chamber atmosphere, 21...Lower steady rest, 22.23...Steel plate, 13
.. 14.24.25...Concrete, 26...Cooling pipe. 7-

Claims (1)

【特許請求の範囲】[Claims] ガードベッセルのないナトリウム機器を収容するコンク
リート製構築物のコンクリート中に冷却管を配設すると
共に、前記構築物のす) IJウム機器に対向する壁面
に鋼板を介し断熱材を設置したことを特徴とする高速増
殖炉のナトリウム機器周辺構築物。
A cooling pipe is installed in the concrete of a concrete structure that accommodates sodium equipment without a guard vessel, and a heat insulating material is installed via a steel plate on the wall of the structure facing the IJium equipment. Structures surrounding the sodium equipment of a fast breeder reactor.
JP57157295A 1982-09-09 1982-09-09 Sodium equipment surrounding construction for fast breeder Pending JPS5946593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57157295A JPS5946593A (en) 1982-09-09 1982-09-09 Sodium equipment surrounding construction for fast breeder

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57157295A JPS5946593A (en) 1982-09-09 1982-09-09 Sodium equipment surrounding construction for fast breeder

Publications (1)

Publication Number Publication Date
JPS5946593A true JPS5946593A (en) 1984-03-15

Family

ID=15646535

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57157295A Pending JPS5946593A (en) 1982-09-09 1982-09-09 Sodium equipment surrounding construction for fast breeder

Country Status (1)

Country Link
JP (1) JPS5946593A (en)

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