JPS6270794A - Pedestal for pressure vessel of nuclear reactor - Google Patents
Pedestal for pressure vessel of nuclear reactorInfo
- Publication number
- JPS6270794A JPS6270794A JP60210159A JP21015985A JPS6270794A JP S6270794 A JPS6270794 A JP S6270794A JP 60210159 A JP60210159 A JP 60210159A JP 21015985 A JP21015985 A JP 21015985A JP S6270794 A JPS6270794 A JP S6270794A
- Authority
- JP
- Japan
- Prior art keywords
- steel plate
- pedestal
- pressure vessel
- space
- cylinder
- 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
- Pressure Vessels And Lids Thereof (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〕
本発明は、原子炉圧力容器を支持する原子炉圧力容器ペ
デスタルに関する。TECHNICAL FIELD OF THE INVENTION The present invention relates to a nuclear reactor pressure vessel pedestal that supports a nuclear reactor pressure vessel.
第7図は沸騰水型原子炉の原子炉建屋内の内部構造を示
す縦断面図である。この原子炉建屋1内には、原子炉格
納容器2が設置されている。この原子炉格納容器2は、
ドライウェル3を画成しており、このドライウェル3は
原子炉Iモカ抑制室4とベント管5を介して連通された
構造となっている。FIG. 7 is a vertical sectional view showing the internal structure inside the reactor building of the boiling water reactor. Inside this reactor building 1, a reactor containment vessel 2 is installed. This reactor containment vessel 2 is
A dry well 3 is defined, and this dry well 3 has a structure in which it is communicated with a reactor I Moka suppression chamber 4 via a vent pipe 5.
また、原子炉格納容器2のドライウェル、3内には原子
炉圧力容器ペデスタル(以下、単にペデスタルという。Furthermore, a reactor pressure vessel pedestal (hereinafter simply referred to as a pedestal) is located within the dry well of the reactor containment vessel 2 and 3.
)6が立設され、このペデスタル6上には原子炉圧力容
器7が支持されている。このペデスタル6は第8図及び
第9図に示された6L造を右する。) 6 is erected, and a reactor pressure vessel 7 is supported on this pedestal 6. This pedestal 6 corresponds to the 6L structure shown in FIGS. 8 and 9.
第8図は第7図に示されたペデスタルの横断面図、第9
図は第8図のペデスタルの部分拡大図であり、ペデスタ
ル6はプレート鋼板を接続して円筒状に組み立てた外筒
鋼板8と内筒鋼板9とから2重円筒状に構成され、内部
に環状空間が形成される。そして、内筒鋼板9と外筒鋼
板8とは、放射状に複数配設されたりブ10にて補強さ
れ、内f!IjIJ4板9および外筒鋼板8の間に形成
された環状空間にコンクリート11が充填された補強構
造となっている。Figure 8 is a cross-sectional view of the pedestal shown in Figure 7;
The figure is a partially enlarged view of the pedestal in Fig. 8. The pedestal 6 is constructed in a double cylindrical shape from an outer steel plate 8 and an inner steel plate 9, which are assembled into a cylindrical shape by connecting plate steel plates, and has an annular shape inside. A space is formed. The inner cylindrical steel plates 9 and the outer cylindrical steel plates 8 are arranged radially in plurality and reinforced with the bulges 10, so that the inner cylindrical steel plates 9 and the outer cylindrical steel plates 8 are arranged radially in plurality and reinforced with the tubes 10. It has a reinforced structure in which an annular space formed between the IjIJ4 plate 9 and the outer cylindrical steel plate 8 is filled with concrete 11.
このように構成されるペデスタル6は、通常運転中は勿
論、地震時または仮想事故時等においても原子炉圧力容
器7を支持するように働く。したがって、ペデスタル6
は各種荷重条件や組合せ荷重に対して十分耐え得るよう
に剛に設計されなければならない。The pedestal 6 configured in this manner works to support the reactor pressure vessel 7 not only during normal operation but also during an earthquake or a hypothetical accident. Therefore, pedestal 6
must be designed to be sufficiently rigid to withstand various loading conditions and combined loads.
ところが、ペデスタル6におりる外筒鋼板8I3よび内
筒鋼板9の板厚は制限されるために、ペデスタル6の強
度向上に限界があった。剛性を高めるためには鋼板8,
9の板厚を厚くすればよいが、鋼板8,9の板厚をある
値以上にするには鋼板同士の接続部に大きな残留ひずみ
等の内部応力が残るため焼鈍しが必要である。しかし、
このような焼鈍しをするとすれば、焼鈍しを行なう設備
が非常に大型化したり、焼鈍し作業に長時間かかり、作
業が煩粗となり、事実上不可能である。このため、焼鈍
しの必要がない板厚を選択せざるを得イ【い。その結果
、外筒鋼板8や内筒鋼板9は板厚に制限を受け、強度上
の制約を受けるので例えば地震時に、大きな荷重がペデ
スタル6に作用した場合、鋼板8.9間の環状空間に充
填されたコンクリート11に破損が生じる危険性があっ
た。However, since the thicknesses of the outer cylindrical steel plate 8I3 and the inner cylindrical steel plate 9 that extend into the pedestal 6 are limited, there is a limit to the strength improvement of the pedestal 6. To increase rigidity, steel plate 8,
However, in order to make the steel plates 8 and 9 thicker than a certain value, annealing is required because internal stress such as large residual strain remains at the joint between the steel plates. but,
If such annealing were to be performed, the equipment for annealing would be extremely large, the annealing work would take a long time, and the work would be complicated, making it virtually impossible. Therefore, it is necessary to select a plate thickness that does not require annealing. As a result, the outer cylindrical steel plate 8 and the inner cylindrical steel plate 9 are limited in thickness and strength, so when a large load is applied to the pedestal 6 during an earthquake, for example, the annular space between the steel plates 8 and 9 is There was a risk that the filled concrete 11 would be damaged.
また、鋼板8,9は熱伝導率に優れるところから、例え
ば冷却材喪失事故時にドライウェル3内が高温状態とな
ったときに、コンクリート11の中央部とその内外周部
との温度差が大きくなり、その熱膨張差によりコンクリ
ート11の破損が生じる危険性があった。第10図はこ
のときの熱伝導概略図であり、Aは温瓜分布を示してい
る。In addition, since the steel plates 8 and 9 have excellent thermal conductivity, when the interior of the dry well 3 reaches a high temperature during a coolant loss accident, for example, there will be a large temperature difference between the center of the concrete 11 and its inner and outer peripheries. Therefore, there was a risk that the concrete 11 would be damaged due to the difference in thermal expansion. FIG. 10 is a schematic diagram of heat conduction at this time, and A shows the warm melon distribution.
(発明の目的〕
本発明は、上述した事情を考慮してなされたもので、鋼
板の板厚を制限範囲内に抑えるとともに、ペデスタルの
剛性を高め、もってペデスタルの信頼性を向上させた原
子炉圧力容器ペデスタルを提供することを目的とする。(Object of the Invention) The present invention has been made in consideration of the above-mentioned circumstances, and is a nuclear reactor that suppresses the thickness of the steel plate within a limited range, increases the rigidity of the pedestal, and thereby improves the reliability of the pedestal. The purpose is to provide a pressure vessel pedestal.
本発明は上述した目的を達成するために、外筒鋼板と内
筒鋼板との間に形成される環状空間内にコンクリートが
充填された原子炉圧力容器ペデスタルにおいて、前記内
筒鋼板および外筒鋼板の少なくとも一方を、外側鋼板と
内側鋼板とから二重筒構造に構成し、前記内側鋼板およ
び外側鋼板間の空間に断熱域を形成したことを特徴とす
るものである。In order to achieve the above-mentioned object, the present invention provides a reactor pressure vessel pedestal in which an annular space formed between an outer cylinder steel plate and an inner cylinder steel plate is filled with concrete. The invention is characterized in that at least one of the steel plates has a double-tube structure made of an outer steel plate and an inner steel plate, and a heat insulating area is formed in the space between the inner steel plate and the outer steel plate.
以下、本発明を図面に示す実施例に基づいて説明する。 Hereinafter, the present invention will be explained based on embodiments shown in the drawings.
第1図は本発明の第1の実施例に係るペデスタルの縦断
面図、第2図はそのペデスタルの横断面図、第3図は第
2図のペデスタルの部分拡大図である。1 is a longitudinal cross-sectional view of a pedestal according to a first embodiment of the present invention, FIG. 2 is a cross-sectional view of the pedestal, and FIG. 3 is a partially enlarged view of the pedestal of FIG. 2.
このペデスタル6が従来のそれと基本的に箕なる点は、
ペデスタル6の内筒鋼板9および外筒鋼板8の構造であ
り、それ以外の構成は従来と同様であるので同じ符号を
付し、説明を省略する。内筒鋼板9は内筒内側鋼板9a
と内筒外側鋼板9bとから2市箇構造に構成され、その
間に環状の空間12が形成される。また、ペデスタル6
の外筒鋼板8も、外筒内側鋼板8aと外筒外側鋼板8b
とから2重筒構造に構成され、その間に環状の空間13
が形成される。そして、このペデスタル6では、第2図
および第3図に示すように各鋼板8B、3b、9a、g
bは、放射状に複数配設されたりブ10にて補強され、
内筒外側鋼板9bと外筒内側鋼板8aとの間にコンクリ
ート11が充填される。また内周内側鋼板9aと内筒外
側鋼板9bとの環状空IJ12および外筒内側鋼板8a
と外筒外側鋼板8bとの環状空間13には空気が満たさ
れ、これらの環状空間12.13は断熱域として形成さ
れる。The basic differences between this pedestal 6 and the conventional one are as follows:
This is the structure of the inner cylindrical steel plate 9 and the outer cylindrical steel plate 8 of the pedestal 6, and the other configurations are the same as the conventional one, so the same reference numerals are given and the explanation will be omitted. The inner cylinder steel plate 9 is an inner cylinder inner steel plate 9a.
It has a two-part structure consisting of the inner cylinder outer steel plate 9b, and an annular space 12 is formed therebetween. Also, pedestal 6
The outer cylinder steel plate 8 also includes an outer cylinder inner steel plate 8a and an outer cylinder outer steel plate 8b.
It has a double cylinder structure, with an annular space 13 between.
is formed. In this pedestal 6, as shown in FIGS. 2 and 3, each steel plate 8B, 3b, 9a, g
A plurality of b are arranged radially or reinforced with b 10,
Concrete 11 is filled between the inner cylinder outer steel plate 9b and the outer cylinder inner steel plate 8a. In addition, the annular hollow IJ12 between the inner peripheral inner steel plate 9a and the inner cylinder outer steel plate 9b and the outer cylinder inner steel plate 8a
An annular space 13 between the outer cylinder outer steel plate 8b and the outer cylinder outer steel plate 8b is filled with air, and these annular spaces 12 and 13 are formed as a heat insulating area.
次に、作用を説明する。Next, the effect will be explained.
このペデスタル6の各鋼板8a、8b、9a。Each steel plate 8a, 8b, 9a of this pedestal 6.
9bはペデスタル6に作用する荷重を支持し、コンクリ
ート11に加わる荷重を低減させるように動く。また、
例えば冷JJI材喪失時等にドライウェル3内が高温状
態になったときには、環状空間12.13は、コンクリ
−1〜11の温度上背を抑制すると共に、コンクリート
11の中央部とその内外周部との温度差を緩和さ゛せる
よう鋤く。第4図はこのときの熱伝導概略図であり、8
は温度分布を示している。9b supports the load acting on the pedestal 6 and moves to reduce the load applied to the concrete 11. Also,
For example, when the inside of the dry well 3 becomes high temperature due to the loss of cold JJI material, the annular space 12.13 suppresses the temperature rise of the concrete 1 to 11, and the central part of the concrete 11 and its inner and outer peripheries. Plow to reduce the temperature difference between the two parts. Figure 4 is a schematic diagram of heat conduction at this time, and 8
shows the temperature distribution.
このような構成・作用を有するペデスタル6によれば、
ペデスタル6の剛性が高まり、原子炉圧ツノ容器7およ
びその他炉内構込物の地震荷重を低減させることができ
、したがって耐震性の向上を図ることができる。また、
冷却材喪失事故時等にコンクリート11の温度上昇が抑
イーIできると共にコンクリート11の中央部とその内
外周部との温度差が緩和される。その結果、ペデスタル
6の信頼性が向上されることとなる。According to the pedestal 6 having such a configuration and action,
The rigidity of the pedestal 6 is increased, and the seismic load on the reactor pressure horn vessel 7 and other reactor structures can be reduced, and the earthquake resistance can therefore be improved. Also,
In the event of a coolant loss accident, etc., the temperature rise of the concrete 11 can be suppressed, and the temperature difference between the central part of the concrete 11 and its inner and outer peripheral parts is alleviated. As a result, the reliability of the pedestal 6 is improved.
第5図は本発明の第2の実施例に係るペデスタルの部分
横断面図である。FIG. 5 is a partial cross-sectional view of a pedestal according to a second embodiment of the invention.
このペデスタル6が第1の実施例のペデスタルと異なる
点は、内筒内側鋼板9aと内筒外側鋼板9bとの環状空
間12、および外筒内側鋼板8aと外筒外側鋼板8bと
の環状空間13に断熱コンクリート等の断熱材14.1
5が充填されていることである。This pedestal 6 is different from the pedestal of the first embodiment in that there is an annular space 12 between the inner cylinder inner steel plate 9a and the inner cylinder outer steel plate 9b, and an annular space 13 between the outer cylinder inner steel plate 8a and the outer cylinder outer steel plate 8b. 14.1 Insulating material such as insulating concrete
5 is filled.
このペデスタル6によれば、第1の実施例と同様の効果
を骨ることができるのは勿論、環状空間12.13に断
熱U14,15が充填されているので、より断熱効果を
高めることができる。According to this pedestal 6, it is possible to achieve the same effect as in the first embodiment, and since the annular space 12.13 is filled with heat insulating elements U14 and 15, the heat insulating effect can be further enhanced. can.
第6図は本発明の第3の実施例に係るペデスタルの縦断
面図である。FIG. 6 is a longitudinal sectional view of a pedestal according to a third embodiment of the present invention.
このペデスタル6が第1の実施例のそれと異なる点は、
環状空間12.13に冷却水を強制循環させるようにし
たところである。即ち、このペデスタル6は、強制水冷
設備16を備えている。この強制水冷設備16は、空間
12.13に対して淡水を給徘する配管17と、この配
管17の途中に介装された熱交換器18とを含んで構成
されている。この熱交換器18としては、例えば非常用
補は冷n1水系の熱交換器が使用される。This pedestal 6 is different from that of the first embodiment as follows:
Cooling water is forced to circulate in the annular spaces 12 and 13. That is, this pedestal 6 is equipped with forced water cooling equipment 16. The forced water cooling equipment 16 includes a pipe 17 for supplying fresh water to the space 12.13, and a heat exchanger 18 interposed in the middle of the pipe 17. As the heat exchanger 18, for example, a cold n1 water type heat exchanger is used as an emergency supplement.
このペデスタル6によれば、第1の実施例と同様の効果
を得ることができることは勿論、空間12.13内を淡
水が循環されるので、よりコンクリ−1−11の温度上
背が規制され、積極的な冷uIを図ることができると共
に、よりコンクリート11の中央部とその内外周部との
温度差が緩和される。According to this pedestal 6, it is possible to obtain the same effect as in the first embodiment, and since fresh water is circulated within the space 12.13, the temperature of the concrete 1-11 is further regulated. , it is possible to achieve positive cooling uI, and the temperature difference between the central part of the concrete 11 and its inner and outer peripheral parts is further alleviated.
なお、本発明は、図示の実施例に限定されず種々の変形
が可能である。例えば、第3の実施例の強制水冷設備1
6の代りに、空間12.13内へ°−空気を循環させる
強制空冷設備を用いても良い。Note that the present invention is not limited to the illustrated embodiment and can be modified in various ways. For example, forced water cooling equipment 1 of the third embodiment
6 may be replaced by a forced air cooling facility that circulates air into the space 12.13.
また、図示の実施例では、内筒鋼板9および外筒鋼板8
の双方を、内側鋼板8a、9aおよび外側鋼板8b、9
bから構成しているが、内筒鋼板9おJ:び外筒鋼板8
のいずれか一方だけを、そのように構成しても良い。Further, in the illustrated embodiment, the inner cylinder steel plate 9 and the outer cylinder steel plate 8
Both inner steel plates 8a, 9a and outer steel plates 8b, 9
It consists of inner cylinder steel plate 9 and outer cylinder steel plate 8.
Only one of them may be configured in this way.
以上詳細に説明したように本発明によれば、内筒鋼板J
3よび外筒鋼板の少なくとも一方を、内側鋼板おにび外
側鋼板から二重筒構造に構成し、上記内(lll鋼板お
よび外側鋼板間に形成される空間に断熱域を形成したの
で、ペデスタルの剛性が高まり、耐震性の向上を図るこ
とができると共に、その信頼性の向上を図ることができ
る。As explained in detail above, according to the present invention, the inner cylinder steel plate J
At least one of the inner steel plate and the outer steel plate is constructed with a double cylinder structure, and a heat insulating area is formed in the space formed between the inner steel plate and the outer steel plate. Rigidity is increased, earthquake resistance can be improved, and reliability can be improved.
第1図は本発明の第1の実施例に係るペデスタルの縦断
面図、第2図は第1図のペデスタルの■−ff線に沿う
横断面図、第3図は第2図のペデスタルの部分拡大図、
第4図は第1図のペデスタルの熱伝導概略図、第5図は
本発明の第2の実施例に係るペデスタルの部分横断面図
、第6図は本発明の第3の実施例に係るペデスタルの縦
断[+i図、第7図は原子炉建屋の縦断面図、第8図は
従来のペデスタルの横断面図、第9図は第8図のペデス
タルの部分拡大図、第10図は第8図のペデスタルの熱
伝導概略図である。
6・・・ペデスタル、8・・・外f14M板、8a・・
・外局内側鋼板、8b・・・外筒外側鋼板、9・・・内
筒鋼板、9a・・・内筒内側鋼板、9b・・・内筒外側
鋼板、10・・・リブ、11・・・コンクリート、12
.13・・・空間。
代理人弁理士 則 近 憲 缶周
三 俣 弘 文$ / 回
$4 図
第 2 図
qイ
$ 3 図
第 7 図
第 lO図1 is a longitudinal cross-sectional view of a pedestal according to a first embodiment of the present invention, FIG. 2 is a cross-sectional view of the pedestal in FIG. 1 taken along the line ■-ff, and FIG. 3 is a cross-sectional view of the pedestal in FIG. Partial enlarged view,
FIG. 4 is a schematic diagram of heat conduction of the pedestal of FIG. 1, FIG. 5 is a partial cross-sectional view of the pedestal according to the second embodiment of the present invention, and FIG. 6 is a diagram of the third embodiment of the present invention. Longitudinal section of the pedestal [Figure +i, Figure 7 is a vertical cross-sectional view of the reactor building, Figure 8 is a cross-sectional view of a conventional pedestal, Figure 9 is a partially enlarged view of the pedestal in Figure 8, Figure 10 is a FIG. 8 is a schematic diagram of heat conduction of the pedestal in FIG. 8; 6...Pedestal, 8...Outer f14M board, 8a...
- Outer station inner steel plate, 8b... Outer cylinder outer steel plate, 9... Inner cylinder steel plate, 9a... Inner cylinder inner steel plate, 9b... Inner cylinder outer steel plate, 10... Rib, 11...・Concrete, 12
.. 13... Space. Representative Patent Attorney Nori Chika Ken Shu
Hirofumi Mitsumata $ / Times $ 4 Figure 2 Figure q I $ 3 Figure 7 Figure 1O Figure
Claims (1)
にコンクリートが充填された原子炉圧力容器ペデスタル
において、前記内筒鋼板および外筒鋼板の少なくとも一
方を、外側鋼板と内側鋼板とから二重筒構造に構成し、
前記内側鋼板および外側鋼板間の空間に断熱域を形成し
たことを特徴とする原子炉圧力容器ペデスタル。 2、前記内側鋼板および外側鋼板間の空間には断熱材が
充填されたことを特徴とする特許請求の範囲第1項記載
の原子炉圧力容器ペデスタル。 3、前記内側鋼板および外側鋼板の空間を密閉構造とし
、この空間に淡水を給排する強制水冷設備を備えたこと
を特徴とする特許請求の範囲第1項記載の原子炉圧力容
器ペデスタル。[Claims] 1. In a reactor pressure vessel pedestal in which an annular space formed between an outer cylinder steel plate and an inner cylinder steel plate is filled with concrete, at least one of the inner cylinder steel plate and the outer cylinder steel plate is , consists of a double cylinder structure from an outer steel plate and an inner steel plate,
A nuclear reactor pressure vessel pedestal, characterized in that a heat insulating area is formed in a space between the inner steel plate and the outer steel plate. 2. The reactor pressure vessel pedestal according to claim 1, wherein the space between the inner steel plate and the outer steel plate is filled with a heat insulating material. 3. The reactor pressure vessel pedestal according to claim 1, characterized in that the space between the inner steel plate and the outer steel plate has a sealed structure, and is equipped with forced water cooling equipment for supplying and discharging fresh water to this space.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60210159A JPS6270794A (en) | 1985-09-25 | 1985-09-25 | Pedestal for pressure vessel of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60210159A JPS6270794A (en) | 1985-09-25 | 1985-09-25 | Pedestal for pressure vessel of nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6270794A true JPS6270794A (en) | 1987-04-01 |
Family
ID=16584738
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60210159A Pending JPS6270794A (en) | 1985-09-25 | 1985-09-25 | Pedestal for pressure vessel of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6270794A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6570950B1 (en) * | 2002-03-11 | 2003-05-27 | Westinghouse Electric Company Llc | Nuclear plant containment with prefabricated component support structure |
| JP2016166833A (en) * | 2015-03-10 | 2016-09-15 | 三菱重工業株式会社 | Reactor container and construction method of reactor container |
-
1985
- 1985-09-25 JP JP60210159A patent/JPS6270794A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6570950B1 (en) * | 2002-03-11 | 2003-05-27 | Westinghouse Electric Company Llc | Nuclear plant containment with prefabricated component support structure |
| JP2016166833A (en) * | 2015-03-10 | 2016-09-15 | 三菱重工業株式会社 | Reactor container and construction method of reactor container |
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