JPS63142298A - Nuclear power facility - Google Patents
Nuclear power facilityInfo
- Publication number
- JPS63142298A JPS63142298A JP61290244A JP29024486A JPS63142298A JP S63142298 A JPS63142298 A JP S63142298A JP 61290244 A JP61290244 A JP 61290244A JP 29024486 A JP29024486 A JP 29024486A JP S63142298 A JPS63142298 A JP S63142298A
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- building
- turbine
- reactor
- class
- 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.)
- Granted
Links
- 238000010276 construction Methods 0.000 claims 1
- 239000011150 reinforced concrete Substances 0.000 description 8
- 238000012423 maintenance Methods 0.000 description 4
- 238000002955 isolation Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910001294 Reinforcing steel Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000004567 concrete Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000011229 interlayer Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
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
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)
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] (Industrial Application Field) The present invention relates to nuclear facilities, and particularly to an improvement in piping structure that can simplify the structure of a turbine building.
（従来の技術）
原子カ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 couplant is usually built adjacent to the reactor building, and the main steam pipe that transfers the steam to drive the turbine runs from the reactor pressure vessel in the reactor building. It is pulled out and placed across both buildings, and its tip is connected to the turbine in 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。Figures 3 and 4 show conventional nuclear facilities of this type.
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
系等の詰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, and 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 part of the reactor pressure vessel 5 penetrates the reactor containment vessel 7 and supplies main steam. Via the isolation valve 8, the main steam pipe tunnel 10 formed by reinforced concrete walls 9 for radiation shielding
Go through the interior and head to turbine building 2. Thereafter, the main steam pipe 6 passes through a main steam pipe tunnel 12 formed by a reinforced concrete wall 11 on an intermediate floor of the turbine building 2, penetrates through each part of the turbine building 2 via a main steam stop valve 13, and reaches the turbine 14. It is connected. This turbine 14
is connected to a generator. Further, inside the turbine building 2, there are installed equipment such as a condenser 15, a condensate demineralizer, a feed water heater, and an exhaust system.
（発明が解決しようとする間層点）
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、
建屋全体がへクラス機能維持を必要とされることになる
。(Interlayer point to be solved by the invention) In the conventional nuclear power facility having the above configuration, the main steam pipe 6 has a very important function in the nuclear power plant, and the main steam pipe 6 is located inside the turbine building 2. Steam stop valve 13
Until now, the earthquake resistance class was designed to maintain A class functionality. Therefore, the turbine building 2, which has a main steam pipe tunnel 12 that maintains A-class functionality, is installed on the middle floor of the building.
The entire building will be required to maintain class functionality.
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７ＭＡ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
う間層点があった。On the other hand, storage equipment other than the main steam pipe 6 in the turbine building 2,
That is, all the equipment such as the turbine 14 has an earthquake resistance class of B class or C class. Therefore, simply because the main steam pipe 6 is installed in the turbine building 2, the entire structure is required to maintain the 7MA class function. Therefore, each component of the turbine building 2, which should originally maintain B class functionality, is maintained with A class functionality. In this way, in order to make the building structure A-class functional, the structure must be more complex and robust than to maintain B-class functionality, and therefore a considerable amount of reinforcing steel and concrete are required. There was a point where the number increased.
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減させ
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 these points, and is a nuclear power plant that can simplify the structure of the turbine building by reducing the amount of building structures such as reinforced concrete by maintaining the full B-class seismic function of the turbine building. The purpose is to provide facilities.
（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 the Problems) The present invention provides a nuclear power facility equipped with a main steam bypass pipe that is branched from a main steam pipe that connects a reactor pressure vessel and a turbine, and whose tip is connected to a condenser. The main steam bypass pipe is characterized in that an auxiliary main steam stop valve is provided at a portion downstream of the position where the main steam bypass pipe branches from the main steam pipe and located within 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
震クラスか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。(Function) In the nuclear facility according to the present invention, an auxiliary main steam stop valve is provided at a portion of the main steam pipe downstream of the point where the main steam bypass pipe branches and located inside the reactor building. Therefore, the range of main steam pipes whose earthquake resistance class is A class function maintenance can be extended up to the auxiliary main steam stop valve, and the main steam pipes downstream from the auxiliary main steam stop valve are earthquake resistance class It would be a good idea to maintain B-class functionality. Therefore, it is possible to maintain the complete B class seismic function of the turbine building.
（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。(Example) An example 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 indicates 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 in the center of the interior of the reactor building 1.
The main steam pipe 6 led out from the upper part of the reactor, as shown in FIG. 1, penetrates the reactor containment vessel 7, passes through the main steam isolation valve 8,
It passes through a main steam pipe tunnel 10 formed by a reinforced concrete wall 9 for radiation shielding, and is connected to a main steam pipe 17 via an auxiliary main steam stop valve 16 disposed within the main steam pipe tunnel 10.
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。As shown in FIG. 1, this main steam pipe 17 passes through a main steam pipe tunnel 12 formed by a reinforced concrete wall 11 on an intermediate floor of the turbine building 2, passes through a main steam stop valve 13, and then passes through a main steam pipe tunnel 12 formed by a reinforced concrete wall 11 on an intermediate floor of the turbine building 2. It is connected to the turbine 14 by passing through each part.
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Ｍ２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 installed in the turbine building M2, as shown in FIG. It is provided.
主蒸気管６には、第６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) that branches from a position upstream of the auxiliary main steam stop valve 16 shown in FIG. The tip is connected to the condenser 15 through a main steam bypass tunnel 18 provided.
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 inner and outer periphery of the reactor building 1, that is, a portion located within 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 range of the main steam pipe 6 where the seismic class is A class function is maintained. can be applied only to the inner and outer peripheral parts of the reactor building 1 whose seismic resistance class is A class function maintenance. For this reason,
The main steam pipe 17 after the auxiliary main steam stop valve 16 can maintain its seismic class B class function.
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内外局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。Also, regarding the main steam bypass pipe, the main steam bypass valve 19 is installed inside and outside the reactor building 1 whose earthquake resistance class is A class function maintenance, so the main steam bypass pipe after the main steam bypass valve 19 is , the earthquake resistance class can be maintained as 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 seismic class A class function maintenance is housed in the reactor building 1, the turbine building 2 can be made to maintain seismic class B class function completely. As a result, the structure can be simplified compared to conventional turbine buildings, and the amount of building structures such as reinforced concrete can be reduced.
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 explained above, in the present invention, the auxiliary main steam stop valve is provided in the part of the main steam pipe located downstream of the main steam bypass pipe branch point in the reactor building, so that the turbine building can be made earthquake resistant. It is possible to maintain complete B class functionality, and the structure of the turbine building can be simplified by reducing the need for building structures such as reinforced concrete.
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■−■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。
出願人代理人 佐 藤 −雄
第２図FIG. 1 is a cross-sectional view of a nuclear power facility showing an embodiment of the present invention, FIG. 2 is a cross-sectional view taken along the line ■-■ in FIG. The diagram is IV-IV in Figure 3.
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. Applicant's agent Mr. Sato Figure 2
Claims (1)
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。 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。[Claims] 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 main steam drawn out from the reactor pressure vessel and whose tip is connected to the turbine. In a nuclear facility equipped with a main steam bypass pipe that branches from the main steam pipe and whose tip is connected to the condenser, reactor construction is performed downstream of the main steam bypass pipe branch point of the main steam pipe. A nuclear power facility characterized by having an auxiliary main steam stop valve installed in the part located indoors. 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 facilities described in paragraph 1.
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 true JPS63142298A (en) | 1988-06-14 |
| JPH0721552B2 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) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108885910A (en) * | 2016-04-27 | 2018-11-23 | 三菱日立电力系统株式会社 | Steam turbine building and nuclear power station |
-
1986
- 1986-12-05 JP JP61290244A patent/JPH0721552B2/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108885910A (en) * | 2016-04-27 | 2018-11-23 | 三菱日立电力系统株式会社 | Steam turbine building and nuclear power station |
| CN108885910B (en) * | 2016-04-27 | 2023-06-02 | 三菱重工业株式会社 | Steam turbine building and nuclear power station |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0721552B2 (en) | 1995-03-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP0057369B1 (en) | Valve support arrangement for a pressurizer vessel in a nuclear power plant | |
| JPS63142298A (en) | Nuclear power facility | |
| JPH0348558Y2 (en) | ||
| JP2613637B2 (en) | Nuclear power plant | |
| JPS6193997A (en) | Turbine housing | |
| JP2709140B2 (en) | Power plant and steam turbine support | |
| JPS61112298U (en) | ||
| Candlish | Advances in constructability | |
| JPH0220960B2 (en) | ||
| JP2592888B2 (en) | Reactor containment vessel | |
| Scott et al. | Additional Aspects of the Enrico Fermi Atomic Power Plant | |
| JPS6311900A (en) | Condenser washer bit | |
| JPS5825360Y2 (en) | Support device for lead-shielded piping | |
| JPS58143296A (en) | Pipeline facility unit in reactor housing | |
| JPS6338511B2 (en) | ||
| JPS582781A (en) | Reactor container | |
| Wahl | Engineering Innovations for Davis-Besse Containment | |
| Burg et al. | Civil Engineering Aspects of the Fermi Atomic Power Station | |
| JPS6024437B2 (en) | Pedestal structure of reactor pressure vessel | |
| JPH0138280B2 (en) | ||
| JPS61231488A (en) | Nuclear reactor containment device | |
| JPS63120296A (en) | Nuclear power facility | |
| JPH03598B2 (en) | ||
| Koehler et al. | Multibarrier Containment for Nuclear Power Plants | |
| JPS5910894A (en) | Method of laying pipe in reactor building |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| S111 | Request for change of ownership or part of ownership |
Free format text: JAPANESE INTERMEDIATE CODE: R313115 |
|
| R350 | Written notification of registration of transfer |
Free format text: JAPANESE INTERMEDIATE CODE: R350 |
|
| EXPY | Cancellation because of completion of term |