JP2592940B2 - Turbine building - Google Patents

Turbine building

Info

Publication number
JP2592940B2
JP2592940B2 JP63305733A JP30573388A JP2592940B2 JP 2592940 B2 JP2592940 B2 JP 2592940B2 JP 63305733 A JP63305733 A JP 63305733A JP 30573388 A JP30573388 A JP 30573388A JP 2592940 B2 JP2592940 B2 JP 2592940B2
Authority
JP
Japan
Prior art keywords
dose
equipment
turbine
turbine building
low
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
JP63305733A
Other languages
Japanese (ja)
Other versions
JPH02151795A (en
Inventor
恵一 綿貫
隆雄 飯島
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
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 Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP63305733A priority Critical patent/JP2592940B2/en
Publication of JPH02151795A publication Critical patent/JPH02151795A/en
Application granted granted Critical
Publication of JP2592940B2 publication Critical patent/JP2592940B2/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (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、原子力発電所においてタービン主機、発電
機およびタービン系の主要設備が配置されているタービ
ン建屋に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a turbine building in which a turbine main engine, a generator, and main equipment of a turbine system are arranged in a nuclear power plant.

(従来の技術) 原子力プラントにおけるタービン建屋は、プラント運
転中の従業員によるパトロールを考慮して遮蔽壁を設置
している。
(Prior Art) In a turbine building of a nuclear power plant, a shielding wall is installed in consideration of patrol by an employee operating the plant.

第2図は、従来のこの種のタービン建屋を示す平面図
であり、原子炉圧力容器で発生した放射性を含む蒸気
は、主蒸気管によりタービン建屋1に導かれ、この蒸気
によりタービン主機のロータが回転駆動される。タービ
ン主機で仕事をした後の蒸気は、タービン建屋1の中央
部に設置されている復水器2で冷却されて復水となり、
種々な設備を経由して原子炉圧力容器へ給水として供給
される。
FIG. 2 is a plan view showing a conventional turbine building of this kind, in which radioactive steam generated in a reactor pressure vessel is guided to a turbine building 1 by a main steam pipe, and the steam is used to rotate a rotor of a turbine main engine. Is driven to rotate. The steam after working in the turbine main engine is cooled by the condenser 2 installed in the central part of the turbine building 1 and condensed,
It is supplied as water to the reactor pressure vessel via various facilities.

ところで、前記タービン建屋1内の設備の中には、復
水器2、復水の水処理を行なう復水過装置3、復水脱
塩装置4、復水器2の真空度を保ってその気体の処理を
行なう気体廃棄物処理設備5、および放射性を含んだ蒸
気によりポンプを駆動して原子炉圧力容器へ給水を行な
うタービン駆動原子炉給水ポンプ6等の高線量機器と、
高圧復水ポンプ9およびモータ駆動原子炉給水ポンプ10
等の低線量機器とがあり、高線量機器が設置される高線
量区域8と低線量機器が設置される低線量区域11との間
には、各々の設備、機器毎に、プラント運転中の作業員
による高線量機器のパトロールを考慮して遮蔽壁7を設
置している。
By the way, some of the equipment in the turbine building 1 includes a condenser 2, a condensing device 3 for condensate water treatment, a condensate desalination device 4, and a condenser 2 with the degree of vacuum maintained. A high-dose equipment such as a gas waste treatment facility 5 for performing gas treatment, and a turbine-driven reactor water supply pump 6 for driving a pump with radioactive steam to supply water to a reactor pressure vessel;
High pressure condensate pump 9 and motor driven reactor feed pump 10
There is a low-dose device such as the like, and between the high-dose region 8 where the high-dose device is installed and the low-dose region 11 where the low-dose device is installed, for each of the facilities and equipment, The shielding wall 7 is installed in consideration of patrol of high-dose equipment by workers.

(発明が解決しようとする課題) 前記従来のタービン建屋においては、各高線量機器を
それぞれ遮蔽するように遮蔽壁7を設置しているため、
遮蔽壁7が非常に多く必要となり、タービン建屋として
の鉄筋、コンクリートの建築物量が多くなるとともに、
定期検査中のアクセスおよび機器の分解点検等の作業
性、搬出入性が遮蔽壁7により阻害されるという問題が
ある。
(Problems to be Solved by the Invention) In the conventional turbine building, the shielding wall 7 is installed so as to shield each high-dose device.
A very large number of shielding walls 7 are required, and the amount of steel and concrete as a turbine building increases,
There is a problem that workability such as access during periodic inspection, disassembly inspection of equipment, and carrying-in / out performance is hindered by the shielding wall 7.

一方、タービン建屋1の定期検査中の被曝は、クラッ
ド低減対策等により非常に小さくなるとともに、運転中
の被曝量は、高線量機器への作業員によるパトロールが
ほとんどである。
On the other hand, the radiation exposure during the periodic inspection of the turbine building 1 becomes extremely small due to measures to reduce cladding and the like, and the radiation exposure during operation is mostly patrol by workers to high-dose equipment.

本発明は、このような点を考慮してなされたもので、
遮蔽壁の低減による鉄筋、コンクリートの建屋物量の低
減、機器配置スペースの有効利用による建屋の縮小、お
よび定期検査中のアクセス、機器の分解点検等の作業
性、搬出入性の改善を図ることができるタービン建屋を
提供することを目的とする。
The present invention has been made in consideration of such points,
To reduce the amount of reinforcing steel and concrete buildings by reducing the number of shielding walls, to reduce the size of buildings by effectively utilizing the equipment placement space, and to improve access during periodic inspections, workability such as disassembly and inspection of equipment, and improvement in portability. The purpose is to provide a turbine building that can be used.

〔発明の構成〕[Configuration of the invention]

(課題を解決するための手段) 本発明は、前記目的を達成する手段として、タービン
主機を駆動した後の蒸気を復水する復水器、復水の水処
理を行なう復水過装置、復水の脱塩を行なう復水脱塩
装置、前記復水器の真空度を保ってその気体の処理を行
なう気体廃棄物処理設備、および放射性を含んだ蒸気に
よりポンプを駆動して原子炉圧力容器へ給水するタービ
ン駆動原子炉給水ポンプ等の高線量機器が設置される高
線量区域と、高圧復水ポンプおよび起動時に原子炉圧力
容器に給水を行なうモータ駆動原子炉給水ポンプなどの
低線量機器が設置される低線量区域とを、平面形状がほ
ぼ直線状をなす遮蔽壁で区分けし、かつ前記高線量区域
に、形状認識と色認識とを行なうTVカメラ、音認識用の
マイクロホン、および漏洩検知用の漏洩検知器などを有
するパトロール設備を設置するようにしたものである。
(Means for Solving the Problems) The present invention provides, as means for achieving the above object, a condenser for condensing steam after driving a turbine main engine, a condensing device for performing condensate water treatment, A condensate desalination apparatus for desalination of water, a gas waste treatment facility for treating the gas while maintaining the degree of vacuum of the condenser, and a reactor pressure vessel driven by a pump driven by radioactive steam A high-dose area in which high-dose equipment such as a turbine-driven reactor feed pump that supplies water to the reactor, and low-dose equipment such as a high-pressure condensate pump and a motor-driven reactor feed pump that supplies water to the reactor pressure vessel at startup A TV camera, a microphone for sound recognition, a leak detection microphone, and a TV camera for performing shape recognition and color recognition in the high-dose area by dividing the low-dose area to be installed from a shielding wall having a substantially linear planar shape. Leak detector for Etc. is obtained so as to set up a patrol equipment with.

(作 用) 本発明に係るタービン建屋においては、高線量機器お
よび低線量機器が、各々まとめて配置されるとともに、
高線量機器が設置される高線量区域と、低線量機器が設
置される低線量区域とが、平面形状がほぼ直線状をなす
遮蔽壁で区分けされる。このため、遮蔽壁の低減化が可
能となるとともに、定期検査中においては、定期検査中
のアクセス、機器分解点検等の作業性、搬出入性の改善
を図ることが可能となる。
(Operation) In the turbine building according to the present invention, the high-dose equipment and the low-dose equipment are arranged collectively,
The high-dose area where the high-dose equipment is installed and the low-dose area where the low-dose equipment is installed are separated by a shielding wall having a substantially linear planar shape. Therefore, the number of shielding walls can be reduced, and during the periodic inspection, it is possible to improve access during the periodic inspection, operability such as disassembly and inspection of equipment, and improvement in carrying-in / out.

また、光線量区域には、形状認識や色認識用のTVカメ
ラ、音認識用のマイクロホン、および漏洩検知用の漏洩
検知器を有するパトロール設備が設置され、高線量機器
のパトロールは、このパトロール設備を用いてなされ
る。このため、作業員の被曝線量の低減を図ることが可
能となる。
In addition, a patrol facility with a TV camera for shape recognition and color recognition, a microphone for sound recognition, and a leak detector for leak detection is installed in the light dose area. This is done using For this reason, it becomes possible to reduce the exposure dose of the worker.

(実施例) 以下、本発明の一実施例を第1図を参照して説明す
る。
Embodiment An embodiment of the present invention will be described below with reference to FIG.

第1図は、本発明に係るタービン建屋の一例を示す平
面図であり、図中、符号1はタービン建屋である。この
タービン建屋1には、原子炉圧力容器で発生した放射性
を含む蒸気が主蒸気配管により導かれ、タービン主機の
ロータを回転させるようになっている。そして、タービ
ン主機を駆動した後の蒸気は、復水器2により冷却され
復水されるようになっている。
FIG. 1 is a plan view showing an example of a turbine building according to the present invention, in which reference numeral 1 denotes a turbine building. In this turbine building 1, steam containing radioactivity generated in the reactor pressure vessel is guided by a main steam pipe to rotate the rotor of the turbine main engine. The steam after driving the turbine main engine is cooled by the condenser 2 and condensed.

この復水器2、復水の水処理を行なう復水過装置
3、復水の脱塩を行なう復水脱塩装置4、復水器2の真
空度を保ってその気体の処理を行なう気体廃棄物処理設
備5、および放射性を含んだ蒸気によりポンプを駆動し
て原子炉圧力容器へ給水を行なうタービン駆動原子炉給
水ポンプ6等の高線量機器は、第1図に示すように高線
量区域8にまとめて配置されている。
The condenser 2, the condensing device 3 for performing condensate water treatment, the condensate desalination device 4 for performing desalination of condensate, and the gas for treating the gas while maintaining the degree of vacuum of the condenser 2. As shown in FIG. 1, high-dose equipment such as a waste treatment facility 5 and a turbine-driven reactor feedwater pump 6 that drives a pump with radioactive steam to supply water to a reactor pressure vessel, as shown in FIG. 8 are arranged together.

また、低い放射性を含んだ復水の水処理後の機器、す
なわち復水過装置3および復水脱塩装置4の下流側の
機器である高圧復水ポンプ9および起動時に原子炉圧力
容器に給水を行なうモータ駆動原子炉給水ポンプ10等の
低線量機器は、第1図に示すように低線量区域11にまと
めて配置されている。そして、この低線量区域11と前記
高線量区域8とは、平面形状がほぼ直線状をなす遮蔽壁
7で区分けされている。
Further, the equipment after the water treatment of the condensate containing low radioactivity, that is, the high-pressure condensate pump 9 which is the equipment downstream of the condensate condenser 3 and the condensate desalinator 4, and supplies water to the reactor pressure vessel at startup. The low-dose devices such as a motor-driven reactor feed pump 10 for performing the above-mentioned operations are collectively arranged in a low-dose area 11 as shown in FIG. The low-dose area 11 and the high-dose area 8 are separated by a shielding wall 7 having a substantially linear planar shape.

高線量区域8には、形状認識、色認識を行なうテレビ
カメラ、音認識を行なうマイクロホン、および漏洩検知
を行なう漏洩検知器を備えたパトロール設備が設置さ
れ、このパトロール設備を用いて高線量区域8のパトロ
ールが行なわれるようになっている。
In the high-dose area 8, a patrol facility equipped with a television camera for performing shape recognition and color recognition, a microphone for performing sound recognition, and a leak detector for performing leak detection is installed. Patrols are being conducted.

特に、タービン系機器の重要な点検項目としては、漏
洩、振動、異常音の有無と状態確認があげられる。これ
らの点検項目に対して、漏洩については漏洩検知器、異
常音についてはマイクロホン、振動、状態確認について
はテレビカメラを各々設置することにより、パトロール
の自動化が計れる。
In particular, important inspection items for turbine-related equipment include the presence / absence of leakage, vibration, abnormal noise, and state confirmation. For these inspection items, the patrol can be automated by installing a leak detector for leaks, a microphone for abnormal sounds, and a television camera for status confirmation.

例えば、回転機器であるタービン駆動原子炉給水ポン
プ6と気体廃棄物処理装置5の近傍には、重要な点検項
目全てを確認する必要があるため、漏洩検知器、マイク
ロホン、テレビカメラ12がそれぞれ設置されている。ま
た、静的機器である復水過装置3、復水脱塩装置4の
近傍には、漏洩の有無の認識が必要であることから、漏
洩検知器13が設置されている。
For example, a leak detector, a microphone, and a television camera 12 are installed in the vicinity of the turbine-driven reactor water supply pump 6 and the gaseous waste treatment equipment 5, which are rotating devices, because it is necessary to check all important inspection items. Have been. In addition, a leak detector 13 is installed near the condensing device 3 and the condensing device 4, which are static devices, because it is necessary to recognize the presence or absence of leakage.

次に、本実施例の作用について説明する。 Next, the operation of the present embodiment will be described.

高線量機器へのパトロールに際しては、テレビカメ
ラ、マイクロホンおよび漏洩検知器等12,13を備えたパ
トロール設備を用い、高線量区域8に作業員が入ること
なく遠隔操作により行なう。これにより運転中に高線量
機器をパトロールする場合であっても、被曝量を大幅に
低減することができる。
Patrol to the high-dose equipment is performed by remote control without using a patrol facility equipped with a television camera, a microphone, a leak detector, and the like 12 and 13 without entering the high-dose area 8. Thereby, even when patrol of the high-dose equipment during operation, the exposure dose can be significantly reduced.

また、遮蔽壁7は、平面形状がほぼ直線状となってい
るので、タービン建屋1としての鉄筋、コンクリートの
建屋物量を大幅に削減でき、また定期検査中のアクセス
および機器の分解点検等の作業性、搬出入性を大幅に向
上させることができる。
In addition, since the shielding wall 7 has a substantially linear planar shape, the amount of reinforcing steel and concrete building as the turbine building 1 can be significantly reduced. Properties and transportability can be greatly improved.

〔発明の効果〕〔The invention's effect〕

以上説明したように本発明は、高線量区域と低線量区
域とを分け、その間に、平面形状がほぼ直線状をなす遮
蔽壁を設け、高線量区域のパトロールは、パトロール設
備を用い遠隔操作で行なうようにしているので、遮蔽壁
の低減化により建屋建築物量の低減を図ることができ
る。また、機器配置の有効利用によるタービン建屋の縮
小、および定期検査中のアクセス、機器の分解点検等の
作業性、搬出入性の向上を図ることができる。また、作
業員の被曝量を低減できる。
As described above, the present invention divides a high-dose area and a low-dose area, and provides a shielding wall having a substantially linear planar shape between them, and patrols of the high-dose area are performed by remote control using patrol equipment. Since it is performed, the amount of building can be reduced by reducing the number of shielding walls. Further, it is possible to reduce the size of the turbine building by effectively utilizing the arrangement of the equipment, improve the access during the periodic inspection, the workability such as the disassembly and inspection of the equipment, and the improvement of the carry-in / out property. In addition, it is possible to reduce the exposure of the worker.

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

第1図は本発明によるタービン建屋の一例を示す平面
図、第2図は従来のタービン建屋を示す平面図である。 1……タービン建屋、2……復水器、3……復水過装
置、4……復水脱塩装置、5……気体廃棄物処理設備、
6……タービン駆動原子炉給水ポンプ、7……遮蔽壁、
8……高線量区域、9……高圧復水ポンプ、10……モー
タ駆動原子炉給水ポンプ、11……低線量区域、12……漏
洩検知器、マイクロホン、テレビカメラ、13……復水
過装置。
FIG. 1 is a plan view showing an example of a turbine building according to the present invention, and FIG. 2 is a plan view showing a conventional turbine building. 1 ... Turbine building, 2 ... Condenser, 3 ... Condenser filter, 4 ... Condensate desalter, 5 ... Gas waste treatment equipment,
6: Turbine-driven reactor feed pump, 7: Shielding wall,
8 High-dose area, 9 High-pressure condensate pump, 10 Motor-driven reactor feed pump, 11 Low-dose area, 12 Leak detector, microphone, television camera, 13 Condensate apparatus.

フロントページの続き (72)発明者 臼井 弘 神奈川県川崎市幸区堀川町66番2 東芝 エンジニアリング株式会社内 (56)参考文献 特開 昭61−292593(JP,A)Continuation of front page (72) Inventor Hiroshi Usui 66-2 Horikawa-cho, Saiwai-ku, Kawasaki-shi, Kanagawa Prefecture Toshiba Engineering Corporation (56) References JP-A-61-292593 (JP, A)

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】高線量機器が設置される高線量区域と、低
線量機器が設置される低線量区域とを、平面形状がほぼ
直線状をなす遮蔽壁で区分けし、かつ前記高線量区域に
遠隔操作可能なパトロール設備を設置したことを特徴と
するタービン建屋。
1. A high-dose area in which high-dose equipment is installed and a low-dose area in which low-dose equipment is installed are separated by a shielding wall having a substantially linear planar shape. Turbine building equipped with patrol equipment that can be remotely controlled.
JP63305733A 1988-12-02 1988-12-02 Turbine building Expired - Lifetime JP2592940B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63305733A JP2592940B2 (en) 1988-12-02 1988-12-02 Turbine building

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63305733A JP2592940B2 (en) 1988-12-02 1988-12-02 Turbine building

Publications (2)

Publication Number Publication Date
JPH02151795A JPH02151795A (en) 1990-06-11
JP2592940B2 true JP2592940B2 (en) 1997-03-19

Family

ID=17948696

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63305733A Expired - Lifetime JP2592940B2 (en) 1988-12-02 1988-12-02 Turbine building

Country Status (1)

Country Link
JP (1) JP2592940B2 (en)

Also Published As

Publication number Publication date
JPH02151795A (en) 1990-06-11

Similar Documents

Publication Publication Date Title
JP2592940B2 (en) Turbine building
WO2019203576A1 (en) Method for dismantling biological shielding concrete in pressurized water reactor type nuclear power plant
KR102061287B1 (en) Dismantling and decontamination system and method of biodegradable concrete of pwr type nuclear power plant
Sissingh et al. Tritium facility at TFTR
KR102035852B1 (en) Decommissioning method of biodegradable concrete of pwr type nuclear power plant
JPH01295198A (en) Radioactive waste gas treatment device
JPS6032638Y2 (en) nuclear power generation equipment
McKibben et al. SRP Purex Plant: 25 years of successful remote operation
JP2011169649A (en) Nuclear reactor well gate and nuclear reactor inspection method
WO1992002021A1 (en) Apparatus for the containment of nuclear meltdown debris
Blackshaw RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959
JPH04305191A (en) Cooling equipment of container
Wright et al. Refurbishing tritium contaminated ion sources
NABABAN Decommissioning plan for research reactors in Indonesia
Leffrang et al. The Bandsaw: A Highly Sophisticated Dismantling Technique for the Karlsruhe Multi Purpose Research Reactor
Willis Today's Nuclear Challenge: Maintenance and Radiation Exposure
Berry et al. WIPP Safety Significant Confinement Ventilation System Design-18490
Parkhurst et al. Radiological assessment of steam generator repair and replacement
Ureda STIR facility decontamination and disposition. Final report
Bae et al. Radiation exposure reduction in APR1400
GW SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747
JPH01267498A (en) Condensate storage facility of nuclear power plant
La Guardia Identification and evaluation of facilitation techniques for decommissioning light water power reactors
JP2020076621A (en) Equipment processing method of nuclear power plant
Willis and Radiation Exposure