JPS61139794A - Earthquake-proof support structure of reactor vessel - Google Patents

Earthquake-proof support structure of reactor vessel

Info

Publication number
JPS61139794A
JPS61139794A JP59261710A JP26171084A JPS61139794A JP S61139794 A JPS61139794 A JP S61139794A JP 59261710 A JP59261710 A JP 59261710A JP 26171084 A JP26171084 A JP 26171084A JP S61139794 A JPS61139794 A JP S61139794A
Authority
JP
Japan
Prior art keywords
vessel
reactor vessel
safety
reactor
support structure
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
JP59261710A
Other languages
Japanese (ja)
Inventor
博 中村
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP59261710A priority Critical patent/JPS61139794A/en
Publication of JPS61139794A publication Critical patent/JPS61139794A/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

  • Buildings Adapted To Withstand Abnormal External Influences (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】 〔発明の技術分野〕 この発明は、液体金属を冷却材とする原子炉容器の耐震
支持構造に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to an earthquake-resistant support structure for a nuclear reactor vessel using liquid metal as a coolant.

〔発明の技術的背景〕[Technical background of the invention]

液体金属を冷却材とする従来の原子炉lこおいては、第
3図に示すように゛炉心1、炉心支持構造物2などは有
底円胴形の原子炉容器3の中に収容されていて、その原
子炉容器3は、その上部7ランジ部4を原子炉建屋基体
5から張り出したペデスタル6に載せて支持されている
。安全容器7は、その支持脚8を除く部分が原子炉容器
3の上方部を除く部分と相似形であり、原子炉容器3の
外側に所定の間隔をあけて同心に、外周に固着垂下した
円筒状支持脚8を介して建屋基体5の段部上に固着され
ている。原子炉容器3と安全容器7間の空所9には液体
金属ナトリウム(以下単に液体と言う)が充満されてい
る。なお、空所9は万一原子炉容器3から冷却材が漏れ
た場合、これを受は入れる。
In a conventional nuclear reactor that uses liquid metal as a coolant, as shown in FIG. The reactor vessel 3 is supported by placing its upper 7 flange portion 4 on a pedestal 6 extending from the reactor building base 5. The safety vessel 7 has a similar shape to that of the reactor vessel 3 except for the upper part thereof, except for the supporting legs 8, and is attached to the outside of the reactor vessel 3 at a predetermined interval and concentrically and fixedly suspended from the outer periphery. It is fixed onto the stepped portion of the building base 5 via cylindrical support legs 8 . The space 9 between the reactor vessel 3 and the safety vessel 7 is filled with liquid metal sodium (hereinafter simply referred to as liquid). In addition, in the event that coolant leaks from the reactor vessel 3, the space 9 will receive it.

原子炉容器3は原子炉発電容量の増大に伴いその寸法容
積が大きくなるので、地震時に対する耐震支持が極めて
必要かつ重要となる。したがって、従来は、前記のよう
に、原子炉容器3の外側に安全容器7を設け、原子炉容
器3と安全容器7間の空所9に液体を充満して耐震支持
構造となし、地震時に原子炉容器3に作用する地震力を
前記液体の慣性力を利用して安全容器7へ伝達すること
により、原子炉容器3の耐震性を高める方法が採ら前記
液体を用いた原子炉容器3の耐震支持・構造は、原子炉
容器3と安全容器7の間隔が小さい程耐震効果の大きい
ことが知られている。他方、原子炉容器3の供用期間中
検査(以下単に検査と言う)として、原子炉容器3の溶
接線の目視検査及び原子炉容器3内の冷却材の連続漏れ
監視並びに安全容器7の溶接線の目視検査などが要請さ
れ、原子炉容器3と安全容器7の間隔はこれら検査を実
施するため最小通常300am程度は確保する必要があ
り、前記液体を用いて原子炉容器3の耐震支持効果を大
きく向上させることは困難である。
As the reactor vessel 3 increases in size and volume as the reactor power generation capacity increases, seismic support against earthquakes becomes extremely necessary and important. Therefore, conventionally, as described above, the safety vessel 7 is provided outside the reactor vessel 3, and the space 9 between the reactor vessel 3 and the safety vessel 7 is filled with liquid to form an earthquake-resistant support structure. A method of increasing the earthquake resistance of the reactor vessel 3 by transmitting the seismic force acting on the reactor vessel 3 to the safety vessel 7 using the inertia force of the liquid is adopted. It is known that the seismic support/structure has a greater seismic effect as the distance between the reactor vessel 3 and the safety vessel 7 is smaller. On the other hand, as an in-service inspection (hereinafter simply referred to as inspection) of the reactor vessel 3, visual inspection of the weld line of the reactor vessel 3, continuous leakage monitoring of the coolant in the reactor vessel 3, and weld line of the safety vessel 7 are carried out. A visual inspection of the reactor vessel 3 and the safety vessel 7 is required, and it is necessary to maintain a minimum distance of approximately 300 am between the reactor vessel 3 and the safety vessel 7 in order to carry out these inspections. It is difficult to improve significantly.

又、前記検査をするための検査装置は液体中で使用する
関係上、その装置の設計上の困難や信頼性の低下などが
問題となる。更に、地震時においては、空所9内の液体
は振動方向において高い圧力上昇を伴うが、この圧力で
原子炉容器3及び安全容器7が構造的に均一に変形する
と、耐震支持効果は大きく低減する。又、前記圧力によ
り原子炉容器3には高い外圧力が作用するが、この外圧
力により原子炉容器3が座屈を起す虞れもある。
Furthermore, since the inspection apparatus for performing the above-mentioned inspection is used in liquid, there are problems such as design difficulties and decreased reliability of the apparatus. Furthermore, during an earthquake, the liquid in the cavity 9 undergoes a high pressure increase in the vibration direction, but if the reactor vessel 3 and the safety vessel 7 are structurally uniformly deformed by this pressure, the seismic support effect is greatly reduced. do. Moreover, although high external pressure acts on the reactor vessel 3 due to the above pressure, there is a possibility that the reactor vessel 3 may buckle due to this external pressure.

〔発明の目的〕[Purpose of the invention]

この発明は、原子炉容器の従来の耐震支持構造における
前記問題点を解決するためなされたもので、原子炉容器
の耐震支持効果を高め、原子炉容器及び安全容器の検査
を容易にする耐震支持構造を提供することを目的とする
This invention was made in order to solve the above-mentioned problems in the conventional earthquake-resistant support structure for a nuclear reactor vessel, and is an earthquake-resistant support that increases the effect of earthquake-resistant support of a nuclear reactor vessel and facilitates inspection of the reactor vessel and safety vessel. The purpose is to provide structure.

〔発明の概要〕[Summary of the invention]

この発明による原子炉容器の耐震支持構造は、原子炉容
器の外周囲と安全容器の内周面とを複数箇所互いに離れ
たリブにより強固に連結し、原子炉容器゛及び安全容器
が設置される建屋基体の穴部内壁面前記安全容器の外側
に安全容器から所定間隔あけて同心に安全容器と相似形
に金属板ライニングを張り詰め、前記の原子炉容器と安
全容器との間及び前記の安全容器とライニングとの間に
それぞれ流体を充満した構成とすることにより、前記目
的を達するものである。
The earthquake-resistant support structure for a reactor vessel according to the present invention firmly connects the outer periphery of the reactor vessel and the inner circumferential surface of the safety vessel by ribs separated from each other at multiple locations, and the reactor vessel and safety vessel are installed. A metal plate lining is placed on the inner wall surface of the hole in the building base on the outside of the safety vessel at a predetermined distance from the safety vessel and concentrically in a similar shape to the safety vessel, and between the reactor vessel and the safety vessel and the safety vessel. The above-mentioned object is achieved by filling the space between the lining and the lining with fluid.

〔発明の実施例〕[Embodiments of the invention]

この発明の一実施例゛を第1図、第2図について説明す
る。
An embodiment of the present invention will be described with reference to FIGS. 1 and 2.

第1図に示すように、炉心1″、炉心支持構造物2など
を収容している有底円胴形の原子炉容器10は、その上
部フランジ部4を、第3図に示す従来の原子炉容器3と
同様に、原子炉建屋基体16から張り出したペデスタル
6に載せて支持されている。その耐震支持構造としては
、原子炉容器10の外側に原子炉容器10から3ooI
IIlを超える所定間隔をあけて、原子炉容器1oの上
方部を除く部分と相似形の安全容器11を複数箇所の互
いに離れたリブ12により強固に同心に連結して設置し
、更に、安全容器11の外側にして建屋基体16の原子
炉容器10及び安全容器11が設置される穴部の内壁面
には、安全容器11から狭い所定間隔をあけて同心に安
全容器11と相似形をなして金属板ライニング14を張
り詰め、原子炉容器10及び安全容器11間の空所13
には不活性ガスである窒素ガス(以下単にガス体と言う
)を、又安全容器11及びライニング14間の狭い空所
15には液体を充満している。
As shown in FIG. 1, a bottomed cylindrical reactor vessel 10 housing a core 1'', a core support structure 2, etc. has an upper flange 4 that is similar to the conventional nuclear reactor vessel 10 shown in FIG. Like the reactor vessel 3, it is supported by being placed on a pedestal 6 that protrudes from the reactor building base 16.As for its seismic support structure, a 3ooI
At a predetermined interval exceeding IIl, safety vessels 11 having a similar shape to the portion of the reactor vessel 1o except for the upper part are firmly connected concentrically by ribs 12 separated from each other in a plurality of places, and On the inner wall surface of the hole in the building base 16 on the outside of the reactor vessel 11 where the reactor vessel 10 and the safety vessel 11 are installed, a hole similar to the safety vessel 11 is formed concentrically with a narrow predetermined distance from the safety vessel 11. The metal plate lining 14 is tightened to fill the space 13 between the reactor vessel 10 and the safety vessel 11.
The space 15 between the safety container 11 and the lining 14 is filled with a liquid.

次に、この発明の耐震支持構造の作用を説明する。地震
時には、原子炉容器1oと安全容器11とはリブ12に
より強固に連結されているので一体となって振動するが
、安全容器11とライニング14間の狭い空所15に充
満した液体の慣性力に基づき原子炉容器10と安全容器
11とは割振されて建屋基体16による支持が安全に持
続される。
Next, the operation of the earthquake-resistant support structure of the present invention will be explained. In the event of an earthquake, the reactor vessel 1o and the safety vessel 11 vibrate together because they are firmly connected by the ribs 12, but the inertia of the liquid filling the narrow space 15 between the safety vessel 11 and the lining 14 causes Based on this, the reactor vessel 10 and the safety vessel 11 are allocated and support by the building base 16 is maintained safely.

原子炉容器10と安全容器11はリブ12で強固fこ連
結されているが、これら両容器10.11簡の空所13
の幅は300mを超えているので、原子炉容器10及び
安全容器11の液漏れ溶接線の検査などを行うに支障の
ないスペースが確保されている。
The reactor vessel 10 and the safety vessel 11 are firmly connected by a rib 12, but there is a gap 13 between the two vessels 10 and 11.
The width of the reactor vessel 10 and the safety vessel 11 is more than 300 m, so there is enough space to inspect the leakage weld lines of the reactor vessel 10 and the safety vessel 11 without any problems.

次に、この発明の他の実施例を説明する。この実施例の
構成は、前記実施例の構成と全く同様であり、ただ第1
図に示す原子炉容器10と安全容器11間の空所13に
ガス体に代えて液体を充満した点のみが相違する。
Next, another embodiment of the invention will be described. The configuration of this embodiment is completely similar to that of the previous embodiment, except for the first embodiment.
The only difference is that the space 13 between the reactor vessel 10 and safety vessel 11 shown in the figure is filled with liquid instead of gas.

この実施例においても地震時には、原子炉容器10と安
全容器11とは一体となって振動するが、安全容器11
とライニング14間の狭い空所15に充満した液体の慣
性力に基づき原子炉容器10と安全容器11とは制振さ
れて建屋基体16による支持が安全に持続されると共に
、原子炉容器10及び安全容器11間の空所15を液体
で充満したことにより、原子炉容器10は内外側共に熱
伝動の良い液体で囲まれる。又、この実施例においても
、原子炉容器10及び安全容器11の検査の際のスペー
スが確保されていることは前記実施例の場合と全く同様
である。
In this embodiment as well, during an earthquake, the reactor vessel 10 and the safety vessel 11 vibrate together, but the safety vessel 11
Based on the inertial force of the liquid filling the narrow space 15 between the reactor vessel 10 and the lining 14, the vibrations of the reactor vessel 10 and the safety vessel 11 are damped and support by the building base 16 is maintained safely, and the reactor vessel 10 and the safety vessel 11 are By filling the space 15 between the safety vessels 11 with liquid, the reactor vessel 10 is surrounded both inside and outside by liquid with good heat transfer. Further, in this embodiment as well, the space for inspecting the reactor vessel 10 and the safety vessel 11 is secured, just as in the case of the previous embodiment.

〔発明の効果〕〔Effect of the invention〕

この発明による原子炉容器の耐震支持構造は、原子炉容
器の外周囲と安全容器の内周面とを互いに離れたリブに
より複数箇所強固に連結すると共に、安全容器の外側建
屋基体穴部の内壁面に安全容器から所定間隔あけて同心
に安全容器と相似形に金属板ライニングを張り詰め、原
子炉容器と安全容器との間及び安全容器とライニングと
の間にそれぞれ流体を特に安全容器とライニングの間に
は液体を充満した構成とすることにより、原子炉容器と
安全容器間の空所には原子炉容器及び安全容器の溶接線
の検量並びに原子炉容器内からの冷却材の連続漏れ監視
を行うに足る検査スペースを確保することができるので
、安全容器とライニング間の間隔は、この空所からの前
記検査が不要となることから十分lこ狭くすることがで
き、流体制震効果の向上により耐震支持性能を向上でき
る効果があり、更に、地震時に振動方向の液体圧力を受
けるライニングは外面を原子炉建屋基体で支持され、他
方、原子炉容器と安全容器とはリブiこより強固°に連
結されているため、その剛性は大となり、地震時の外圧
による原子炉容器及び安全容器の座屈などの虞れはなく
なり耐震支持構造の健全性が向上する効果がある。
The earthquake-resistant support structure for a reactor vessel according to the present invention firmly connects the outer periphery of the reactor vessel and the inner circumferential surface of the safety vessel at a plurality of locations using ribs spaced apart from each other, and also connects the outer periphery of the reactor vessel and the inner circumferential surface of the safety vessel at multiple locations, and A metal plate lining is placed concentrically on the wall at a predetermined distance from the safety vessel in a similar shape to the safety vessel, and fluid is inserted between the reactor vessel and the safety vessel and between the safety vessel and the lining, especially between the safety vessel and the lining. By filling the space between the reactor vessel and the safety vessel with liquid, the space between the reactor vessel and the safety vessel can be used for calibration of the weld lines of the reactor vessel and safety vessel, and for continuous leakage monitoring of coolant from inside the reactor vessel. The space between the safety container and the lining can be made sufficiently narrow as the inspection from this space is no longer necessary, and the fluid seismic effect can be minimized. This improvement has the effect of improving seismic support performance.Furthermore, the outer surface of the lining, which receives liquid pressure in the vibration direction during an earthquake, is supported by the reactor building base, while the reactor vessel and safety vessel are made stronger by the ribs. Since the reactor vessel and the safety vessel are connected to each other, their rigidity is high, and there is no risk of buckling of the reactor vessel and safety vessel due to external pressure during an earthquake, which has the effect of improving the soundness of the earthquake-resistant support structure.

原子炉容器と安全容器との間及び安全容器とライニング
との間に同一液体を充満する場合は、原子炉容器は内外
側共に熱伝動の良好な同一流体で囲まれることになり、
原子炉容器の温度分布は一様となり、発生する熱応力の
低減に大きな効果がある。
If the same liquid is filled between the reactor vessel and the safety vessel and between the safety vessel and the lining, the reactor vessel will be surrounded both inside and outside by the same fluid with good heat transfer.
The temperature distribution in the reactor vessel becomes uniform, which has a great effect on reducing the thermal stress that occurs.

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

第1図はこの発明の一実施例の縦断面図、第2図は第1
図■−■断面における断面図、第3図は従来の原子炉容
器の耐震支持構造の縦断面図である。 10・・・原子炉容器、11・・・安全容器、12・・
・リブ、14・・・ライニング、16・・・原子炉建屋
基体。 (7317)  代理人 弁理士 則近憲佑(ほか1名
) 第1図 第3図
FIG. 1 is a longitudinal sectional view of one embodiment of the present invention, and FIG.
FIG. 3 is a longitudinal sectional view of a conventional seismic support structure for a reactor vessel. 10...Reactor vessel, 11...Safety vessel, 12...
- Rib, 14... Lining, 16... Reactor building base. (7317) Agent Patent attorney Kensuke Norichika (and 1 other person) Figure 1 Figure 3

Claims (3)

【特許請求の範囲】[Claims] (1)原子炉炉心とその関連装置とを内包し上部フラン
ジ部を原子炉建屋基体から張り出したペデスタル上に支
持される有底円胴形原子炉容器と、この原子炉容器の上
方部を除く部分に相似形にして原子炉容器の外側に所定
の間隔をあけて同心に設置される安全容器とを備えた原
子炉容器の耐震支持構造において、前記原子炉容器の外
周囲と前記安全容器の内周面とを複数箇所互いに離れた
リブにより強固に連結し、前記の原子炉容器及び安全容
器が設置される前記建屋基体の穴部内壁面前記安全容器
の外側に安全容器から所定間隔あけて同心に安全容器と
相似形に金属板ライニングを張り詰め、前記の原子炉容
器と安全容器との間及び前記の安全容器とライニングと
の間にそれぞれ流体を充満したことを特徴とする原子炉
容器の耐震支持構造。
(1) Excluding the bottomed cylindrical reactor vessel containing the reactor core and related equipment and whose upper flange is supported on a pedestal extending from the reactor building base, and the upper part of this reactor vessel. In an earthquake-resistant support structure for a reactor vessel, the structure includes a safety vessel that is similar in shape to the outer circumference of the reactor vessel and is installed concentrically at a predetermined interval on the outside of the reactor vessel. The inner peripheral surface is firmly connected to the inner peripheral surface by ribs spaced apart from each other at a plurality of places, and the inner wall surface of the hole in the building base where the reactor vessel and safety vessel are installed is concentric with the safety vessel at a predetermined distance from the safety vessel. A reactor vessel characterized in that a metal plate lining is stretched in a similar shape to the safety vessel, and a fluid is filled between the reactor vessel and the safety vessel and between the safety vessel and the lining, respectively. Seismic support structure.
(2)原子炉容器と安全容器との間に充満される流体が
不活性ガスにして、安全容器とライニングとの間に充満
される流体が液体金属であることを特徴とする特許請求
の範囲第1項に記載の原子炉容器の耐震支持構造。
(2) Claims characterized in that the fluid filled between the reactor vessel and the safety vessel is an inert gas, and the fluid filled between the safety vessel and the lining is a liquid metal. Earthquake-resistant support structure for the reactor vessel described in paragraph 1.
(3)原子炉容器と安全容器間、安全容器とライニング
間にそれぞれ充満される流体が液体金属であることを特
徴とする特許請求の範囲第1項に記載の原子炉容器の耐
震支持構造。
(3) The seismic support structure for a reactor vessel according to claim 1, wherein the fluid filled between the reactor vessel and the safety vessel and between the safety vessel and the lining is liquid metal.
JP59261710A 1984-12-13 1984-12-13 Earthquake-proof support structure of reactor vessel Pending JPS61139794A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59261710A JPS61139794A (en) 1984-12-13 1984-12-13 Earthquake-proof support structure of reactor vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59261710A JPS61139794A (en) 1984-12-13 1984-12-13 Earthquake-proof support structure of reactor vessel

Publications (1)

Publication Number Publication Date
JPS61139794A true JPS61139794A (en) 1986-06-27

Family

ID=17365630

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59261710A Pending JPS61139794A (en) 1984-12-13 1984-12-13 Earthquake-proof support structure of reactor vessel

Country Status (1)

Country Link
JP (1) JPS61139794A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01242996A (en) * 1988-03-24 1989-09-27 Toshiba Corp Fast breeder

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01242996A (en) * 1988-03-24 1989-09-27 Toshiba Corp Fast breeder

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