JPS63195594A - Nuclear reactor plant - Google Patents
Nuclear reactor plantInfo
- Publication number
- JPS63195594A JPS63195594A JP62026289A JP2628987A JPS63195594A JP S63195594 A JPS63195594 A JP S63195594A JP 62026289 A JP62026289 A JP 62026289A JP 2628987 A JP2628987 A JP 2628987A JP S63195594 A JPS63195594 A JP S63195594A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- containment vessel
- water
- vessel
- pool
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 96
- 238000002955 isolation Methods 0.000 claims description 14
- 238000001816 cooling Methods 0.000 claims description 11
- 239000000446 fuel Substances 0.000 claims description 9
- 239000000498 cooling water Substances 0.000 claims 2
- 241000196324 Embryophyta Species 0.000 description 16
- 230000002093 peripheral effect Effects 0.000 description 16
- 230000001629 suppression Effects 0.000 description 11
- 238000002347 injection Methods 0.000 description 9
- 239000007924 injection Substances 0.000 description 9
- 238000010276 construction Methods 0.000 description 5
- 239000007921 spray Substances 0.000 description 5
- 238000009835 boiling Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 239000002915 spent fuel radioactive waste Substances 0.000 description 4
- 238000009833 condensation Methods 0.000 description 3
- 230000005494 condensation Effects 0.000 description 3
- 230000004888 barrier function Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000005574 cross-species transmission Effects 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000010612 desalination reaction Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 108010053481 Antifreeze Proteins Proteins 0.000 description 1
- 235000008331 Pinus X rigitaeda Nutrition 0.000 description 1
- 235000011613 Pinus brutia Nutrition 0.000 description 1
- 241000018646 Pinus brutia Species 0.000 description 1
- 238000010795 Steam Flooding Methods 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000004378 air conditioning Methods 0.000 description 1
- 230000002528 anti-freeze Effects 0.000 description 1
- 230000003749 cleanliness Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000011010 flushing procedure Methods 0.000 description 1
- 238000001802 infusion Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000009423 ventilation 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
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation 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】
［産業上の利用分野］
本発明は、原子炉プラントに係り、特に原子炉建屋内に
復水貯蔵プールを設けた原子炉プラントに関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a nuclear reactor plant, and particularly to a nuclear reactor plant in which a condensate storage pool is provided within a reactor building.
［従来の技術］
特開昭５４−１３７５９６号公報に示された従来の沸騰
水型原子炉プラントは、復水貯蔵タンクを原子炉建屋及
びタービン建屋に近接させて原子炉建屋の屋外に設置し
である。この復水貯蔵タンクは、燃料プール補給水系、
制御棒駆動水圧系の水源、給復水系の保有水量調整用に
用いられいた。[Prior Art] A conventional boiling water reactor plant disclosed in Japanese Patent Application Laid-Open No. 54-137596 has a condensate storage tank installed outside the reactor building in close proximity to the reactor building and the turbine building. It is. This condensate storage tank is used for fuel pool make-up water system,
It was used as a water source for the control rod drive hydraulic system and for adjusting the amount of water held in the water supply and condensation system.
また、安全系である原子炉隔離時冷却系、高圧炉心スプ
レィ系の水源としても用いていた。It was also used as a water source for the safety systems such as the reactor isolation cooling system and the high-pressure core spray system.
［発明が解決しようとする問題点］
従来の沸騰水型原子炉プラントは、復水貯蔵タンクは、
専用に設けられた耐震基礎マット（コンクリートマット
）上に設置されていた。このため。[Problems to be solved by the invention] In a conventional boiling water reactor plant, the condensate storage tank is
It was installed on a specially prepared earthquake-resistant foundation mat (concrete mat). For this reason.
上記専用の耐震基礎マットを構築するにあたり多量のコ
ンクリートを必要とし、沸騰水型原子炉プラントの全基
礎マットの構築に長時間を要していた。A large amount of concrete was required to construct the above-mentioned dedicated seismic foundation mat, and it took a long time to construct all the foundation mats for a boiling water reactor plant.
本発明の目的は、上記従来例の問題点を解消し。An object of the present invention is to solve the problems of the conventional example described above.
建設期間を短縮できる原子炉プラントを提供することに
ある。The objective is to provide a nuclear reactor plant that can shorten the construction period.
［問題を解決するための手段］
上記の目的は、格納容器とこの周囲をとり囲む筒状の生
体じゃへい体との間に、復水貯蔵プールを設けることに
よって達成させることが出来る。[Means for Solving the Problem] The above object can be achieved by providing a condensate storage pool between the containment vessel and the cylindrical living body surrounding the containment vessel.
［作用コ
原子炉格納容器外周プール（復水貯蔵プール）は原子炉
格納容器外側に配置され、また、注入ポンプ、ポンプ駆
動タービン、主蒸気管および注入配管は原子炉格納容器
、原子炉建屋に配置される。[Applications] The reactor containment vessel outer peripheral pool (condensate storage pool) is located outside the reactor containment vessel, and the injection pump, pump drive turbine, main steam pipe, and injection piping are located in the reactor containment vessel and reactor building. Placed.
故に原子炉格納容器外周プールに接近して接続すること
が可能なため、原子炉隔離時冷却系及び緊急炉心冷却系
（ＥＣＣ５）等の安全系、制御棒駆動装置の駆動水系、
及び燃料プール補給水系等の原子炉建屋内の重要度の高
い配管のルートを非常に短くすることが出来る。Therefore, since it is possible to connect close to the outer peripheral pool of the reactor containment vessel, safety systems such as the reactor isolation cooling system and the emergency core cooling system (ECC5), the drive water system of the control rod drive device,
The route of highly important piping inside the reactor building, such as the fuel pool make-up water system, can be extremely shortened.
また、格納容器外周プールは原子炉格納容器と原子炉建
屋の生体じゃへい壁（コンクリート壁）との間に形成さ
れる余剰空間部に配置されるため、原子炉建屋の耐震コ
ンクリートマット上に設置されることになる。従って、
本発明は、従来の原子炉プラントで必要としていた復水
貯蔵タンク専用の耐震コンクリートマットが不用となる
ので１本発明の耐震基礎マットに必要なコンクリート打
設量が大巾に低減でき、基礎マットの構築期間、ひいて
は原子炉プラントの建設期間を短縮できる。In addition, since the containment vessel outer pool is located in the surplus space formed between the reactor containment vessel and the biological barrier wall (concrete wall) of the reactor building, it is installed on the earthquake-resistant concrete mat of the reactor building. will be done. Therefore,
The present invention eliminates the need for earthquake-resistant concrete mats dedicated to condensate storage tanks, which were required in conventional nuclear reactor plants. This can shorten the construction period of nuclear power plants and, by extension, the construction period of nuclear reactor plants.
ここで、従来の復水貯蔵タンクの機能を有する格納容器
外周プールを原子炉建屋内に設置する場合、約２００Ｏ
ｎ−１’以上の水を原子炉建屋内に保有することとなり
、万一の漏洩時に対し、その検出及び漏洩水による他の
設備１例えば非常用炉心冷１設備への溢水防止を考慮し
てお（必要がある。Here, when installing a containment vessel outer circumferential pool that has the function of a conventional condensate storage tank in the reactor building, approximately 200 O
Water of n-1' or more will be kept in the reactor building, and in the event of a leak, consideration will be given to detecting it and preventing leaked water from overflowing to other equipment, such as emergency core cooling equipment. Oh (I need it.
格納容器外周プールは、ライニングプール構造になる。The outer peripheral pool of the containment vessel has a lining pool structure.
このようにライニングプール構造にする場合は従来の使
用済燃料プールの漏洩検出設備と同等の設備を設置する
ことにより容易にライニング溶接部等からの漏洩検出が
可能になる。また、格納容器外周プールの大破損等によ
り多量の保有水が漏洩した場合においても第５図に示す
ように生体じゃへい壁５０が溢水防止壁として機能する
。When using a lined pool structure as described above, leakage from lining welds etc. can be easily detected by installing equipment equivalent to leakage detection equipment for conventional spent fuel pools. Further, even if a large amount of retained water leaks due to major damage to the outer circumferential pool of the containment vessel, the biological barrier wall 50 functions as a water overflow prevention wall, as shown in FIG. 5.
したがって生体しやへい壁外に設置されている他の安全
上重要な機器が溢水にみまわれる様な事態は生じない。Therefore, there is no possibility that other safety-important equipment installed outside the living room wall will be flooded with water.
さらに、格納容器外周プールを復水貯蔵タンクの代替設
備とするためにはその水質を規定値に維持しておく必要
がある。ここで格納容器外周プールは原子炉格納容器内
のサプレッションプールと異なり主蒸気逃がし安全弁の
排気や残留熱除去系のフラッシング水等の流入がなく、
水質悪化の要因がない、したがって格納容器外周プール
水質はプラント寿命期間を通じてその清浄度を十分維持
することが可能と考えられ１．従来の復水貯蔵タンクと
しての機能を十分達成することができる。Furthermore, in order to use the containment vessel peripheral pool as an alternative to the condensate storage tank, it is necessary to maintain its water quality at a specified value. Here, unlike the suppression pool inside the reactor containment vessel, the containment vessel peripheral pool does not have the main steam relief safety valve exhaust or residual heat removal system flushing water flowing into it.
1. There are no factors that deteriorate water quality, and therefore it is considered possible to maintain sufficient cleanliness of the water quality in the outer pool of the containment vessel throughout the life of the plant.1. It can fully function as a conventional condensate storage tank.
［実施例］
以下１本発明の一実施例である沸騰水型原子炉プラント
を第１図及び第５図により説明する。[Embodiment] A boiling water nuclear reactor plant which is an embodiment of the present invention will be described below with reference to FIGS. 1 and 5.
原子炉圧力容器１内で発生した蒸気は主蒸気管８にてタ
ービン４６に送られる。タービン４６から排気された蒸
気は、復水器４０にて凝縮されて水となる。この凝縮水
は、給水として復水ポンプ４８、復水ろ過脱塩装置４１
、給水ポンプ４７及び給水加熱器４３が設けられた給水
復水配管５９により原子炉圧力容器１に戻される。Steam generated within the reactor pressure vessel 1 is sent to the turbine 46 through the main steam pipe 8. Steam exhausted from the turbine 46 is condensed into water in the condenser 40. This condensed water is supplied to a condensate pump 48 and a condensate filter desalination device 41 as water supply.
, the feed water is returned to the reactor pressure vessel 1 through a feed water condensate pipe 59 provided with a feed water pump 47 and a feed water heater 43.
格納容器外周プール４は、第５図に詳細に示すように原
子炉格納容器２と原子炉建屋の生体じゃへい壁５０との
間に形成され、しかも環状のプールである。原子炉圧力
容器１の周囲を取囲むサプレッションチェンバ（圧力抑
制室）３Ａ及び格納容器外周プール４は、原子炉建屋の
耐震コンクリートマット５３上に設置される。サプレッ
ションチェンバ３Ａ及び格納容器外周プール４内には、
プール水３及び４Ａが充填されている。原子炉格納容器
２内のドライウェル５４は、ベント通路５５によってサ
プレッションプール水３中に連絡されている。As shown in detail in FIG. 5, the containment vessel outer peripheral pool 4 is formed between the reactor containment vessel 2 and the biological wall 50 of the reactor building, and is an annular pool. A suppression chamber (pressure suppression chamber) 3A surrounding the reactor pressure vessel 1 and a containment vessel outer peripheral pool 4 are installed on an earthquake-resistant concrete mat 53 of the reactor building. Inside the suppression chamber 3A and the containment vessel outer peripheral pool 4,
Pool water 3 and 4A are filled. A dry well 54 in the reactor containment vessel 2 is connected to the suppression pool water 3 by a vent passage 55.
格納容器外周プール４には、復水ろ過説塩装置４１下流
で給水復水配管５９より分岐されたスピルオーバライン
配管４２が接続されるとともに、格納容器外周プール水
移送ポンプ４４を有する補給ライン配管４５が接続され
、給復水系の保有水調整ができるようになっている。補
給ライン配管４５は復水器４０に連絡される。A spillover line piping 42 branched from a water supply condensate piping 59 downstream of the condensate filtration salt theory device 41 is connected to the containment vessel outer circumferential pool 4, and a supply line piping 45 having a containment vessel outer circumferential pool water transfer pump 44 is connected. is connected, allowing adjustment of the water held in the water supply and condensation system. Supply line piping 45 is connected to condenser 40 .
一方、原子炉隔離事象却ポンプ６の吸込配管１１が格納
容器外周プ、−ル４に接続されている。On the other hand, the suction pipe 11 of the reactor isolation pump 6 is connected to the containment vessel outer circumferential pipe 4.
原子炉水位低の信号により主蒸気配管８に設けられた主
蒸気隔離弁６０が急閉する原子炉隔離時に、原子炉隔離
時冷却装置は、自動起動して原子炉格納容器外周プール
４内のプール水４Ａをポンプ吸込配管１１を介して注入
ポンプ６によって昇圧し、注入配管１３を介し原子炉圧
力容器Ｉに注入する。また、水源である原子炉格納容器
外周プール４内のプール水４Ａの水位が低下した場合に
は、サプレッションチェンバ３Ａのプール水３に水源を
切替え運転を継続する。During reactor isolation, when the main steam isolation valve 60 provided in the main steam piping 8 suddenly closes due to a low reactor water level signal, the reactor isolation cooling system automatically starts and closes the main steam isolation valve 60 provided in the main steam piping 8 suddenly. The pool water 4A is pressurized by the injection pump 6 via the pump suction pipe 11 and is injected into the reactor pressure vessel I via the injection pipe 13. Furthermore, when the water level of the pool water 4A in the reactor containment vessel outer peripheral pool 4, which is a water source, decreases, the water source is switched to the pool water 3 of the suppression chamber 3A and operation is continued.
注入ポンプ６は、７によって駆動される。原子炉水位低
信号により隔離弁６１が開きタービン、原子炉圧力容器
１で発生した蒸気が主蒸気管８、及び蒸気供給配管９を
介してタービン７に導びかれる。この蒸気によるタービ
ン７の回転により注入ポンプ６が駆動される。タービン
７から排気された蒸気は、タービン排気管１４を介して
サプレッションチェンバ３Ａ内のプール水３にて凝縮、
回収される。Infusion pump 6 is driven by 7. The isolation valve 61 is opened by the reactor water level low signal, and the steam generated in the turbine and the reactor pressure vessel 1 is guided to the turbine 7 via the main steam pipe 8 and the steam supply pipe 9. The rotation of the turbine 7 by this steam drives the injection pump 6. The steam exhausted from the turbine 7 is condensed in the pool water 3 in the suppression chamber 3A via the turbine exhaust pipe 14.
It will be collected.
このように何らかの原因で原子炉隔離事象が生じた場合
、上記の原子炉隔離時冷却装置の運転に基づき炉心から
の崩壊熱を除去することができる。In this manner, when a reactor isolation event occurs for some reason, decay heat from the reactor core can be removed based on the operation of the reactor isolation cooling device described above.
またこの時同時に冷却材喪失事故が発生した場合でも、
格納容器２内のドライウェル５４に放出された蒸気の熱
を格納容器外周プール４に移送し静的除熱を行なうこと
ができる。すなわち、ドライウェル５４内の蒸気は、ベ
ント通路５１を介してサプレッションチェンバ３Ａ内の
プール水３中に導かれ凝縮する。この蒸気凝縮によるプ
ール水３の温度が上昇するが、プール水３の温度は、格
納容器（鋼製）２の側壁を介して復水貯蔵プール４のプ
ール水４Ａに伝えられる。この場合には格納容器外周プ
ール水４への除熱時に必要な水を確保する為に原子炉隔
離時冷却装置を自動停止させるインターロックを設ける
。さらに、格納容器外周プール４のプール水４Ａは原子
炉隔離時冷却設備の注水量と冷却材喪失事故時の熱除去
に際しての蒸発量の合計量を確保できるように充填され
ている。Also, even if a coolant loss accident occurs at the same time,
The heat of the steam released into the dry well 54 in the containment vessel 2 can be transferred to the containment vessel outer peripheral pool 4 for static heat removal. That is, the steam in the dry well 54 is guided into the pool water 3 in the suppression chamber 3A via the vent passage 51 and condensed therein. The temperature of the pool water 3 increases due to this steam condensation, but the temperature of the pool water 3 is transmitted to the pool water 4A of the condensate storage pool 4 via the side wall of the containment vessel (made of steel) 2. In this case, an interlock is provided to automatically stop the reactor isolation cooling system in order to secure water necessary for heat removal to the containment vessel outer peripheral pool water 4. Furthermore, the pool water 4A in the containment vessel outer peripheral pool 4 is filled in such a manner that the total amount of water injected into the reactor isolation cooling equipment and evaporated during heat removal in the event of a loss of coolant accident can be ensured.
第２図は緊急炉心冷却装置の一系統である高圧炉心スプ
レィ装置の水源として格納容器外周プール４のプール水
４Ａを利用した実施例である。この高圧炉心スプレィ装
置は、第１図に示す構造と併用されているものである。FIG. 2 shows an embodiment in which pool water 4A of the containment vessel peripheral pool 4 is used as a water source for a high-pressure core spray device, which is one system of the emergency core cooling system. This high-pressure core spray device is used in combination with the structure shown in FIG.
第２図に示す高圧炉心スプレィ装置は、原子炉水位低信
号（Ｍ子方隔離時冷却装置を駆動させる原子炉水位低信
号よりもレベルが低い）により自動起動し、原子炉格納
容器外周プール４内のプール水４Ａをポンプ吸込配管１
１Ａを介して注入ポンプ６Ａによって昇圧し、注入配管
１３Ａを介し原子炉圧力容器１の炉心内に注入する。The high-pressure core spray device shown in Figure 2 is automatically activated by a low reactor water level signal (lower in level than the low reactor water level signal that drives the M isolation cooling system), and Pump 4A of pool water inside suction pipe 1
1A by the injection pump 6A, and injected into the core of the reactor pressure vessel 1 via the injection pipe 13A.
又、水源である原子炉格納容器外周プール水４の水位が
低下した場合には、サプレッションチェンバ３Ａ内のプ
ール水３に水源を切替え運転を継続する。Further, when the water level of the reactor containment vessel outer peripheral pool water 4, which is the water source, decreases, the water source is switched to the pool water 3 in the suppression chamber 3A and operation is continued.
第３図は、制御棒駆動装置駆動水供給装置の水源として
格納容器外周プール４内のプール水４Ａを使用した実施
例である。本実施例の系統も、第１図の構造と併用され
る。格納容器外周プール４内のプール水４Ａは、サクシ
ョンフィルタ２０を介し制御棒駆動水ポンプ２１により
昇圧され、原子炉圧力容器１内の炉心に挿入される制御
棒（図示せず）を操作する制御棒駆動装置２２に駆動水
として供給される。２３は水圧制御ユニットである。FIG. 3 shows an embodiment in which pool water 4A in the outer circumferential pool 4 of the containment vessel is used as the water source for the control rod drive device drive water supply device. The system of this embodiment is also used in combination with the structure of FIG. Pool water 4A in the containment vessel peripheral pool 4 is pressurized by a control rod drive water pump 21 via a suction filter 20, and is controlled to operate control rods (not shown) inserted into the core in the reactor pressure vessel 1. It is supplied to the rod drive device 22 as driving water. 23 is a water pressure control unit.
第４図は、燃料プール補給水供給装置の水源として格納
容器外周プール４内のプール水４Ａを使用した実施例で
ある。本実施例の系統も、第１図の構造と併用される。FIG. 4 shows an embodiment in which pool water 4A in the outer circumferential pool 4 of the containment vessel is used as the water source for the fuel pool make-up water supply system. The system of this embodiment is also used in combination with the structure of FIG.
この燃料プール補給水装置は、地層時通常の補給水設備
が使用できない場合にスロッシングにより溢水した使用
済燃料プール水の補給を行なうものである。格納容器外
周プール４内のプール水４Ａは燃料プール補給水ポンプ
３０により昇圧され使用済燃料プール３１へ補給される
。This fuel pool make-up water system replenishes spent fuel pool water that overflows due to sloshing when normal make-up water equipment cannot be used. Pool water 4A in the containment vessel outer circumferential pool 4 is pressurized by the fuel pool makeup water pump 30 and replenished to the spent fuel pool 31.
以上述べた本実施例によれば、従来プラントの復水貯蔵
タンクに相当する復水貯蔵プールである格納容器外周プ
ールを原子炉建屋の中心部の基礎マツ１〜上に設置する
ことができ、原子炉建屋内に設置される重要度の高いプ
ール配管系（第１図、第２図、第４図の事故時に供用す
る配管系、第３図の制御棒駆動装置駆動水供給装置）の
配管長を著しく短縮することができる。また、原子炉建
屋耐震マット上に直接設置しているため従来プラントの
如く復水貯蔵タンク専用の耐震マットの設置が不用とな
りプラントの建設期間短縮が図れる。According to the present embodiment described above, the containment vessel outer circumferential pool, which is a condensate storage pool corresponding to a condensate storage tank in a conventional plant, can be installed above the foundation pines 1 to 1 in the center of the reactor building. Piping for the highly important pool piping system installed in the reactor building (the piping system used in the event of an accident in Figures 1, 2, and 4, and the control rod drive drive water supply system in Figure 3) The length can be significantly shortened. In addition, since it is installed directly on the earthquake-resistant mat of the reactor building, there is no need to install an earthquake-resistant mat dedicated to the condensate storage tank as in conventional plants, and the construction period of the plant can be shortened.
さらに、従来プラントの如く復水貯蔵タンクを屋外に設
置する必要がないため凍結防止用ヒータ等の保温設備が
不要であり、原子炉建屋内の換気空調設備により外気温
度によらず適正温度に維持することができる。Furthermore, unlike in conventional plants, there is no need to install a condensate storage tank outdoors, so there is no need for heat insulation equipment such as anti-freeze heaters, and ventilation and air conditioning equipment inside the reactor building maintains the temperature at an appropriate level regardless of outside temperature. can do.
［発明の効果］
本発明によれば、従来必要とした復水貯蔵タンク専用の
基礎マットが不要になるので、原子炉プラントの建設期
間を短縮できる。[Effects of the Invention] According to the present invention, a foundation mat dedicated to a condensate storage tank, which was conventionally required, is no longer necessary, so that the construction period of a nuclear reactor plant can be shortened.
第１図は、本発明の一実施例である原子炉プラントの構
成図、第２図は第１図の実施例に用いられる高圧炉心ス
プレィ装置の構成図、第３図は第１図の実施例に用いら
れる制御棒駆動装置駆動水供給装置の構成図、第４図は
第１図の実施例に用いられる燃料プール補給水供給装置
の構成図、第５図は第１図の実施例で系統植成を除いた
構築物の構成図である。
１・・・原子炉圧力容器、２・・・原子炉格納容器、３
・・・サプレッションプール水、４・・・原子炉格納容
器外周プール水、５・・・復水貯蔵タンク、６・・・注
入ポンプ、７・・・ポンプ駆動タービン、８・・・主蒸
気管、９・・・蒸気供給配管、１０・・・ポンプ吸込配
管（復水貯蔵タンク側）、１１・・・ポンプ吸込配管（
原子炉格納容器外周プール側）、１２・・・ポンプ吸込
配管（サプレッションチェンバ側）、１３・・・注入配
管、１４・・・タービン排気管、１５・・・テスト配管
（Ｍ子方格納容器外周プール側）、１６・・・テスト配
管（復水貯蔵タンク側）、２０・・・サクションフィル
タ、２１・・・制御棒駆動水ポンプ、２２・・・制御棒
駆動機構、２３・・・水圧制御ユニット
３０・・・燃料プール補給水ポンプ、３１・・・使用済
燃料プール
４０・・・復水器、４１・・・復水ろ過脱塩装置、４２
・・・スピルオーバーライン配管、４３・・・給水加熱
器。
４４・・・格納容器外周プール水移送ポンプ、４５・・
・補給ライン
５０・・・生体しやへい壁、５１・・・ベント壁、５２
・・・第１図
第２図
第３図
第ヰ図□Fig. 1 is a block diagram of a nuclear reactor plant that is an embodiment of the present invention, Fig. 2 is a block diagram of a high-pressure core spray device used in the embodiment of Fig. 1, and Fig. 3 is an implementation of the system shown in Fig. 1. FIG. 4 is a block diagram of the fuel pool make-up water supply system used in the embodiment of FIG. 1, and FIG. FIG. 2 is a configuration diagram of the construct excluding phylogenetic planting. 1... Reactor pressure vessel, 2... Reactor containment vessel, 3
... Suppression pool water, 4... Reactor containment vessel outer peripheral pool water, 5... Condensate storage tank, 6... Injection pump, 7... Pump drive turbine, 8... Main steam pipe , 9... Steam supply piping, 10... Pump suction piping (condensate storage tank side), 11... Pump suction piping (
12...Pump suction pipe (suppression chamber side), 13...Injection pipe, 14...Turbine exhaust pipe, 15...Test pipe (M child containment vessel outer circumference) pool side), 16... Test piping (condensate storage tank side), 20... Suction filter, 21... Control rod drive water pump, 22... Control rod drive mechanism, 23... Water pressure control Unit 30... Fuel pool makeup water pump, 31... Spent fuel pool 40... Condenser, 41... Condensate filtration desalination device, 42
...Spill over line piping, 43...Feed water heater. 44... Containment vessel outer circumference pool water transfer pump, 45...
・Supply line 50... Living wall, 51... Vent wall, 52
...Figure 1 Figure 2 Figure 3 Figure □
Claims (1)
ット上に設置されるとともに前記格納容器の周囲を取囲
む筒状の生体しやへい体と、前記格納容器内に設置され
る原子炉容器と、前記原子炉容器と復水器とを連絡する
給水管路と、前記格納容器と前記生体しやへい体との間
に設けられて前記給水管路に連絡された復水貯蔵プール
とを備えた原子炉プラント。 ２、基礎マット上に設置された格納容器と、前記基礎マ
ット上に設置されるとともに前記格納容器の周囲を取囲
む筒状の生体しやへい体と、前記格納容器内に設置され
る原子炉容器と、前記原子炉容器と復水器とを連絡する
給水管路と、前記格納容器と前記生体しやへい体との間
に設けられて前記給水管路に連絡された復水貯蔵プール
と、原子炉の隔離時に前記復水貯蔵プール内の冷却水を
前記原子炉容器内に導く原子炉隔離時冷却装置とを備え
た原子炉プラント。 ３、基礎マット上に設置された格納容器と、前記基礎マ
ット上に設置されるとともに前記格納容器の周囲を取囲
む筒状の生体しやへい体と、前記格納容器内に設置され
る原子炉容器と、前記原子炉容器と復水器とを連絡する
給水管路と、前記格納容器と前記生体しやへい体との間
に設けられて前記給水管路に連絡された復水貯蔵プール
と、前記原子炉容器内に設置された制御棒を操作する制
御棒駆動装置に前記復水貯蔵プール内の冷却水を導く制
御棒駆動装置駆水供給装置とを備えた原子炉プラント。 ４、基礎マット上に設置された格納容器と、前記基礎マ
ット上に設置されるとともに前記格納容器の周囲を取囲
む筒状の生体しやへい体と、前記格納容器内に設置され
る原子炉容器と、前記原子炉容器と復水器とを連絡する
給水管路と、前記格納容器と前記生体しやへい体との間
に設けられて前記給水管路に連絡された復水貯蔵プール
と、前記復水貯蔵プール内のプール水を燃料貯蔵プール
に導く燃料プール水補給装置とを備えた原子炉プラント
。[Scope of Claims] 1. A containment vessel installed on a base mat, a cylindrical living body that is installed on the base mat and surrounds the containment vessel, and a container inside the containment vessel. A reactor vessel installed in the reactor vessel, a water supply pipe connecting the reactor vessel and the condenser, and a water supply pipe provided between the containment vessel and the living body and communicating with the water supply pipe. A nuclear reactor plant with a condensate storage pool. 2. A containment vessel installed on a basic mat, a cylindrical living body that is installed on the basic mat and surrounds the containment vessel, and a nuclear reactor installed in the containment vessel. a vessel, a water supply pipe connecting the reactor vessel and the condenser, and a condensate storage pool provided between the containment vessel and the living body and communicating with the water supply pipe. . A nuclear reactor plant comprising: a reactor isolation cooling device that guides cooling water in the condensate storage pool into the reactor vessel when the reactor is isolated. 3. A containment vessel installed on a foundation mat, a cylindrical living body that is installed on the foundation mat and surrounds the containment vessel, and a nuclear reactor installed in the containment vessel. a vessel, a water supply pipe connecting the reactor vessel and the condenser, and a condensate storage pool provided between the containment vessel and the living body and communicating with the water supply pipe. A nuclear reactor plant comprising: a control rod drive water supply device that guides cooling water in the condensate storage pool to a control rod drive device that operates control rods installed in the reactor vessel. 4. A containment vessel installed on a foundation mat, a cylindrical living body that is installed on the foundation mat and surrounds the containment vessel, and a nuclear reactor installed in the containment vessel. a vessel, a water supply pipe connecting the reactor vessel and the condenser, and a condensate storage pool provided between the containment vessel and the living body and communicating with the water supply pipe. , a fuel pool water supply device for guiding pool water in the condensate storage pool to a fuel storage pool.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62026289A JPS63195594A (en) | 1987-02-09 | 1987-02-09 | Nuclear reactor plant |
| US07/098,530 US5011652A (en) | 1986-09-19 | 1987-09-18 | Nuclear power facilities |
| KR1019870010357A KR950009881B1 (en) | 1986-09-19 | 1987-09-18 | Neclear power facilities |
| CN87106445A CN1012769B (en) | 1986-09-19 | 1987-09-18 | Nuclear-powered apparatus |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62026289A JPS63195594A (en) | 1987-02-09 | 1987-02-09 | Nuclear reactor plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63195594A true JPS63195594A (en) | 1988-08-12 |
| JPH0471479B2 JPH0471479B2 (en) | 1992-11-13 |
Family
ID=12189140
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62026289A Granted JPS63195594A (en) | 1986-09-19 | 1987-02-09 | Nuclear reactor plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63195594A (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5364189A (en) * | 1976-11-19 | 1978-06-08 | Hitachi Ltd | Suppression chamber |
-
1987
- 1987-02-09 JP JP62026289A patent/JPS63195594A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5364189A (en) * | 1976-11-19 | 1978-06-08 | Hitachi Ltd | Suppression chamber |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0471479B2 (en) | 1992-11-13 |
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