JPH0721552B2 - Nuclear facility - Google Patents

Nuclear facility

Info

Publication number
JPH0721552B2
JPH0721552B2 JP61290244A JP29024486A JPH0721552B2 JP H0721552 B2 JPH0721552 B2 JP H0721552B2 JP 61290244 A JP61290244 A JP 61290244A JP 29024486 A JP29024486 A JP 29024486A JP H0721552 B2 JPH0721552 B2 JP H0721552B2
Authority
JP
Japan
Prior art keywords
main steam
building
turbine
pipe
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.)
Expired - Lifetime
Application number
JP61290244A
Other languages
Japanese (ja)
Other versions
JPS63142298A (en
Inventor
恵一 綿貫
弘 臼井
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 JP61290244A priority Critical patent/JPH0721552B2/en
Publication of JPS63142298A publication Critical patent/JPS63142298A/en
Publication of JPH0721552B2 publication Critical patent/JPH0721552B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

Landscapes

  • Buildings Adapted To Withstand Abnormal External Influences (AREA)
  • Supply And Distribution Of Alternating Current (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Crystals, And After-Treatments Of Crystals (AREA)

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は原子力施設に係り、特にタービン建屋の構造を
簡素化できる配管構造の改良に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) The present invention relates to a nuclear facility, and more particularly to an improvement of a piping structure capable of simplifying the structure of a turbine building.

(従来の技術) 原子力プラントにおけるタービン建屋は、通常原子炉建
屋に隣接して建てられており、タービンを駆動するため
の蒸気を移送する主蒸気管は、原子炉建屋内の原子炉圧
力容器から引出され、両建屋に亘って配されて先端がタ
ービン建屋内のタービンに接続されている。
(Prior Art) The turbine building in a nuclear power plant is usually built adjacent to the reactor building, and the main steam pipe that transfers steam for driving the turbine is from the reactor pressure vessel inside the reactor building. It is pulled out and placed across both buildings, and the tip is connected to the turbine inside the turbine building.

第3図および第4図は、従来のこの種の原子力施設を示
している。
3 and 4 show a conventional nuclear facility of this kind.

同図に示すように、原子炉建屋1とタービン建屋2とは
隣接しており、原子炉建屋1は原子炉建屋基礎3の上
に、またタービン建屋2はタービン建屋基礎4の上に建
てられている。原子炉建屋1内の中央部には、原子炉圧
力容器5が設けられており、この原子炉圧力容器5の上
部から導出された主蒸気管6は原子炉格納容器7を貫通
し、主蒸気隔離弁8を経て、放射線遮蔽のために鉄筋コ
ンクリート壁9によって形成された主蒸気管トンネル10
内を通ってタービン建屋2へ向かう。その後前記主蒸気
管6は、タービン建屋2の中間階に鉄筋コンクリート壁
11によって形成された主蒸気管トンネル12内を通り、主
蒸気止め弁13を介してタービン建屋2の各部を貫通しタ
ービン14へ接続されている。このタービン14には発電機
が連結されている。また、このタービン建屋2内には、
復水器15や復水脱塩器、給水加熱器、排気系等の諸機器
が設けられている。
As shown in the figure, the reactor building 1 and the turbine building 2 are adjacent to each other, the reactor building 1 is built on the reactor building foundation 3, and the turbine building 2 is built on the turbine building foundation 4. ing. A reactor pressure vessel 5 is provided in the center of the reactor building 1, and a main steam pipe 6 led out from the upper portion of the reactor pressure vessel 5 penetrates the reactor containment vessel 7 Main steam pipe tunnel 10 formed by reinforced concrete wall 9 for radiation shielding through isolation valve 8
Head inside to Turbine Building 2. After that, the main steam pipe 6 is installed on the middle floor of the turbine building 2 on a reinforced concrete wall.
It passes through a main steam pipe tunnel 12 formed by 11 and penetrates each part of the turbine building 2 through a main steam stop valve 13 and is connected to a turbine 14. A generator is connected to the turbine 14. In addition, in this turbine building 2,
Various devices such as a condenser 15, a condensate demineralizer, a feed water heater, and an exhaust system are provided.

(発明が解決しようとする問題点) 以上の構成を有する従来の原子力施設において、主蒸気
管6は、原子力発電プラントにおいては非常に重要な機
能を有しており、タービン建屋2内の主蒸気止め弁13ま
では、耐震クラスをAクラス機能維持として設計されて
いる。そのため、Aクラス機能維持の主蒸気管トンネル
12を建屋の中間階に設けているタービン建屋2も、建屋
全体がAクラス機能維持を必要とされることになる。
(Problems to be Solved by the Invention) In the conventional nuclear facility having the above configuration, the main steam pipe 6 has a very important function in the nuclear power plant, and the main steam in the turbine building 2 is Up to stop valve 13, the seismic class is designed to maintain Class A function. Therefore, the main steam pipe tunnel that maintains A-class function
The turbine building 2, which has 12 on the middle floor of the building, also needs to maintain A-class function for the entire building.

一方、タービン建屋2内の主蒸気管6以外の収納機器、
すなわちタービン14等のすべての機器は、その耐震クラ
スがBクラスまたはCクラスである。したがって、ター
ビン建屋2は単に主蒸気管6を設置するだけのために、
全体を耐震Aクラス機能維持を必要とされていることに
なる。そのため、本来Bクラス機能維持で良いはずのタ
ービン建屋2の構成各部をもAクラス機能維持にしてい
る。このように、建屋の構造をAクラス機能維持にする
ことは、Bクラス機能維持にすることに比べて、その構
造を複雑かつ堅牢にしなければならず、そのため鉄筋お
よびコンクリートもともに相当に量が多くなるという問
題点があった。
On the other hand, storage equipment other than the main steam pipe 6 in the turbine building 2,
That is, all equipment such as the turbine 14 has a seismic class of B class or C class. Therefore, the turbine building 2 simply installs the main steam pipe 6,
It means that it is necessary to maintain seismic A-class function as a whole. For this reason, the constituent parts of the turbine building 2 which are originally supposed to be able to maintain the B class function are also maintained in the A class function. In this way, maintaining the structure of the building in the A class function requires making the structure more complicated and robust than maintaining the B class function, and therefore the amount of both the reinforcing bar and concrete is considerably large. There was a problem that it would increase.

本発明はこのような点を考慮してなされたもので、ター
ビン建屋を耐震クラス完全Bクラス機能維持にすること
により、鉄筋コンクリート等の建築構造物量を低滅させ
てタービン建屋の構造を簡素化できる原子力施設を提供
することを目的とする。
The present invention has been made in consideration of such a point, and by keeping the turbine building functioning as a seismic class complete B class, the structure of the turbine building can be simplified by reducing the amount of building structures such as reinforced concrete. The purpose is to provide nuclear facilities.

〔発明の構成〕[Structure of Invention]

(問題点を解決するための手段) 本発明は、原子炉圧力容器とタービンとを接続する主蒸
気管から分岐され、先端が復水器に接続されている主蒸
気バイパス管を備えた原子力施設であって、この主蒸気
バイパス管が主蒸気管から分岐する位置よりも下流側
で、かつ原子炉建屋内に位置する部分に、補助主蒸気止
め弁を設けるようにしたことを特徴としている。
(Means for Solving Problems) The present invention relates to a nuclear facility equipped with a main steam bypass pipe branched from a main steam pipe connecting a reactor pressure vessel and a turbine and having a tip connected to a condenser. The main steam bypass pipe is provided with an auxiliary main steam stop valve at a portion located downstream of the position where the main steam pipe branches from the main steam pipe and inside the reactor building.

(作 用) 本発明に係る原子力施設においては、主蒸気管の主蒸気
バイパス管が分岐する位置よりも下流側で、かつ原子炉
建屋内に位置する部分に、補助主蒸気止め弁を設けるよ
うにしているので、耐震クラスがAクラス機能維持であ
る主蒸気管の範囲を、補助主蒸気止め弁までとすること
ができ、補助主蒸気止め弁より下流側の主蒸気管は、耐
震クラスがBクラス機能維持でよいことになる。このた
め、タービン建屋を耐震クラス完全Bクラス機能維持と
することが可能となる。
(Operation) In the nuclear facility according to the present invention, an auxiliary main steam stop valve should be provided at a portion located downstream of the main steam bypass pipe branching position and inside the reactor building. Therefore, the range of the main steam pipes whose seismic resistance class is A class function maintenance can be extended to the auxiliary main steam stop valve, and the main steam pipes downstream from the auxiliary main steam stop valve have seismic resistance class. It will be good to maintain the B class function. For this reason, it becomes possible to maintain the turbine building in a seismic resistant class B class function.

(実施例) 以下本発明の一実施例を第1図および第2図を参照して
説明する。
(Embodiment) An embodiment of the present invention will be described below with reference to FIGS. 1 and 2.

図において、符号1はタービン建屋2と隣接する原子炉
建屋であり、原子炉建屋1は原子炉建屋基礎3上に、ま
たタービン建屋2はタービン建屋基礎4上に建てられて
いる。
In the figure, reference numeral 1 is a reactor building adjacent to a turbine building 2, the reactor building 1 is built on a reactor building foundation 3, and the turbine building 2 is built on a turbine building foundation 4.

原子炉建屋1の内部中央には、第2図に示すように原子
炉圧力容器5が設けられており、この原子炉圧力容器5
の上部から導出された主蒸気管6は、第1図に示すよう
に原子炉格納容器7を貫通し、主蒸気隔離弁8を経て、
放射線遮蔽のために鉄筋コンクリート壁9によって形成
された主蒸気管トンネル10内を通り、この主蒸気管トン
ネル10内に配した補助主蒸気止め弁16を介し主蒸気管17
に接続されている。
As shown in FIG. 2, a reactor pressure vessel 5 is provided at the center of the inside of the reactor building 1.
As shown in FIG. 1, the main steam pipe 6 led out from the upper part of the reactor penetrates the reactor containment vessel 7, passes through the main steam isolation valve 8, and
A main steam pipe 17 is passed through a main steam pipe tunnel 10 formed by a reinforced concrete wall 9 for radiation shielding, and an auxiliary main steam stop valve 16 arranged in the main steam pipe tunnel 10 is used.
It is connected to the.

この主蒸気管17は、第1図に示すようにタービン建屋2
の中間階に鉄筋コンクリート壁11によって形成された主
蒸気管トンネル12内を通り、主蒸気止め弁13を経て、そ
の後タービン建屋2の各部を貫通してタービン14へ接続
されている。
This main steam pipe 17 is connected to the turbine building 2 as shown in FIG.
It passes through the main steam pipe tunnel 12 formed by the reinforced concrete wall 11 on the middle floor of the above, passes through the main steam stop valve 13, and then penetrates each part of the turbine building 2 and is connected to the turbine 14.

タービン14には、発電機が連結されており、またタービ
ン建屋2内には、第2図に示すように復水器15や復水脱
塩器、給水加熱器、排気系等の諸機器が設けられてい
る。
A generator is connected to the turbine 14, and various equipment such as a condenser 15, a condensate demineralizer, a feed water heater, and an exhaust system are provided in the turbine building 2 as shown in FIG. It is provided.

主蒸気管6には、第1図に示す補助主蒸気止め弁16の上
流位置から分岐する主蒸気バイパス管(図示せず)が設
けられており、この主蒸気バイパス管は、タービン建屋
2に設けた主蒸気バイパストンネル18内を通して先端が
復水器15に接続されている。
The main steam pipe 6 is provided with a main steam bypass pipe (not shown) branched from the upstream position of the auxiliary main steam stop valve 16 shown in FIG. 1. The main steam bypass pipe is provided in the turbine building 2. The tip is connected to the condenser 15 through the provided main steam bypass tunnel 18.

この主蒸気バイパス管の原子炉建屋1内外周部に位置す
る部位、すなわち主蒸気管トンネル10内に位置する部位
には、第1図に示すように主蒸気バイパス弁19が設置さ
れている。
As shown in FIG. 1, a main steam bypass valve 19 is installed at a portion of the main steam bypass pipe located on the outer periphery of the reactor building 1, that is, a portion located inside the main steam pipe tunnel 10.

以上の構成において、原子炉建屋1内に位置する主蒸気
管6の先端には、補助主蒸気止め弁16が接続されている
ので、耐震クラスがAクラス機能維持である主蒸気管6
の範囲を、耐震クラスがAクラス機能維持である原子炉
建屋1内外周部のみとすることができる。このため、補
助主蒸気止め弁16以降の主蒸気管17は、耐震クラスがB
クラス機能維持とすることができる。
In the above configuration, since the auxiliary main steam stop valve 16 is connected to the tip of the main steam pipe 6 located in the reactor building 1, the main steam pipe 6 whose seismic class is A class function maintenance.
It is possible to limit the range to only the inner and outer peripheral portions of the reactor building 1 whose seismic class is A class function maintenance. For this reason, the main steam pipe 17 after the auxiliary main steam stop valve 16 has a seismic class B
The class function can be maintained.

また、主蒸気バイパス管についても、主蒸気バイパス弁
19が、耐震クラスがAクラス機能維持である原子炉建屋
1内外周部に設置されているので、主蒸気バイパス弁19
以降の主蒸気バイパス管は、耐震クラスをBクラス機能
維持とすることができる。
The main steam bypass valve is also used for the main steam bypass pipe.
19 is installed in the outer periphery of the reactor building 1 whose seismic class is A class function maintenance, so the main steam bypass valve 19
Subsequent main steam bypass pipes can maintain seismic class B class function.

このように、耐震クラスがAクラス機能維持を必要とす
る設備を原子炉建屋1内に納めているので、タービン建
屋2を耐震クラス完全Bクラス機能維持とすることがで
きる。これにより、従来のタービン建屋に比べてその構
造の簡略化が可能となり、鉄筋コンクリート等の建築構
造物の低減を図ることができる。
In this way, since the equipment that requires the seismic resistant class to maintain the A class function is housed in the reactor building 1, the turbine building 2 can maintain the seismic resistant class complete B class function. As a result, the structure of the turbine building can be simplified as compared with the conventional turbine building, and the building structure such as reinforced concrete can be reduced.

〔発明の効果〕〔The invention's effect〕

以上説明したように本発明は、主蒸気管の主蒸気バイパ
ス管分岐点より下流側で原子炉建屋内に位置する部分
に、補助主蒸気止め弁を設けるようにしているので、タ
ービン建屋を耐震クラス完全Bクラス機能維持とするこ
とができ、鉄筋コンクリート等の建築構造物を低減させ
てタービン建屋の構造を簡素化できる。
As described above, according to the present invention, the auxiliary main steam stop valve is provided in the portion located inside the reactor building on the downstream side of the main steam bypass pipe branch point of the main steam pipe. Class complete B class function can be maintained, building structures such as reinforced concrete can be reduced, and the structure of the turbine building can be simplified.

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

第1図は本発明の一実施例を示す原子力施設の横断面
図、第2図は第1図のII−II線断面図、第3図は従来の
原子力施設を示す横断面図、第4図は第3図のIV−IV線
断面図である。 1……原子炉建屋、2……タービン建屋、5……原子炉
圧力容器、6,17……主蒸気管、15……復水器、16……補
助主蒸気止め弁、19……主蒸気バイパス弁。
FIG. 1 is a cross sectional view of a nuclear facility showing an embodiment of the present invention, FIG. 2 is a cross sectional view taken along the line II-II of FIG. 1, and FIG. 3 is a transverse sectional view showing a conventional nuclear facility. The drawing is a sectional view taken along the line IV-IV in FIG. 1 ... Reactor building, 2 ... Turbine building, 5 ... Reactor pressure vessel, 6,17 ... Main steam pipe, 15 ... Condenser, 16 ... Auxiliary main steam stop valve, 19 ... Main Steam bypass valve.

───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭63−9896(JP,A) 特開 昭62−28694(JP,A) 実開 昭54−180900(JP,U) ─────────────────────────────────────────────────── ─── Continuation of the front page (56) References JP-A-63-9896 (JP, A) JP-A-62-28694 (JP, A) Actually developed JP-A-54-180900 (JP, U)

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】原子炉圧力容器が設置される原子炉建屋と
タービンおよび復水器が設置されるタービン建屋と、前
記原子炉圧力容器から引出され先端がタービンに接続さ
れる主蒸気管と、この主蒸気管から分岐し先端が前記復
水器に接続される主蒸気バイパス管とを備えた原子力施
設において、前記主蒸気管の主蒸気バイパス管分岐点よ
り下流側で原子炉建屋内に位置する部分に、補助主蒸気
止め弁を設けたことを特徴とする原子力施設。
1. A reactor building in which a reactor pressure vessel is installed, a turbine building in which a turbine and a condenser are installed, and a main steam pipe which is drawn from the reactor pressure vessel and whose tip is connected to a turbine. In a nuclear facility equipped with a main steam bypass pipe branching from this main steam pipe and having a tip connected to the condenser, the main steam bypass pipe branch point of the main steam pipe is located downstream of the main steam bypass pipe in the reactor building. A nuclear facility characterized in that an auxiliary main steam stop valve was installed in the part to be operated.
【請求項2】主蒸気バイパス管は主蒸気バイパス弁を有
し、この主蒸気バイパス弁は、主蒸気バイパス管の原子
炉建屋内に位置する部分に設けられていることを特徴と
する特許請求の範囲第1項記載の原子力施設。
2. The main steam bypass pipe has a main steam bypass valve, and the main steam bypass valve is provided in a portion of the main steam bypass pipe located inside the reactor building. Nuclear facility according to paragraph 1 of the above.
JP61290244A 1986-12-05 1986-12-05 Nuclear facility Expired - Lifetime JPH0721552B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61290244A JPH0721552B2 (en) 1986-12-05 1986-12-05 Nuclear facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61290244A JPH0721552B2 (en) 1986-12-05 1986-12-05 Nuclear facility

Publications (2)

Publication Number Publication Date
JPS63142298A JPS63142298A (en) 1988-06-14
JPH0721552B2 true JPH0721552B2 (en) 1995-03-08

Family

ID=17753622

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61290244A Expired - Lifetime JPH0721552B2 (en) 1986-12-05 1986-12-05 Nuclear facility

Country Status (1)

Country Link
JP (1) JPH0721552B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2017187563A1 (en) * 2016-04-27 2017-11-02 三菱日立パワーシステムズ株式会社 Turbine building and nuclear power plant

Also Published As

Publication number Publication date
JPS63142298A (en) 1988-06-14

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