JPH06174890A - Device for isolating main steam piping from secondary reactor container - Google Patents
Device for isolating main steam piping from secondary reactor containerInfo
- Publication number
- JPH06174890A JPH06174890A JP43A JP32835292A JPH06174890A JP H06174890 A JPH06174890 A JP H06174890A JP 43 A JP43 A JP 43A JP 32835292 A JP32835292 A JP 32835292A JP H06174890 A JPH06174890 A JP H06174890A
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- containment vessel
- reactor
- reactor container
- reactor containment
- 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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、沸騰水型原子力プラン
トの主蒸気配管における原子炉格納容器を内包する原子
炉二次格納容器の隔離に係り、特に主蒸気配管破断事故
時にタービン建屋等を隔離する主蒸気配管の原子炉二次
格納容器隔離装置に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to isolation of a secondary reactor containment vessel containing a reactor containment vessel in a main steam pipe of a boiling water nuclear power plant, and particularly to a turbine building or the like in the event of a main steam pipe breakage accident. The present invention relates to a reactor secondary containment isolation device for a main steam pipe to be isolated.
【０００２】[0002]
【従来の技術】従来の沸騰水型原子力発電プラントにお
いては、図２の主蒸気系統構成図に示すように、原子炉
圧力容器１を格納した原子炉格納容器２は、原子炉建屋
の原子炉二次格納容器３に内包されている。2. Description of the Related Art In a conventional boiling water nuclear power plant, as shown in the main steam system configuration diagram of FIG. 2, a reactor containment vessel 2 containing a reactor pressure vessel 1 is a reactor of a reactor building. It is contained in the secondary storage container 3.
【０００３】放射性物質を内包する原子炉圧力容器１内
で発生した蒸気は、原子炉格納容器２および原子炉二次
格納容器３を貫通する主蒸気配管４を通じて、タービン
建屋５内に設置された主タービン６および主復水器７へ
送り込まれている。The steam generated in the reactor pressure vessel 1 containing the radioactive material is installed in the turbine building 5 through the main steam pipe 4 penetrating the reactor containment vessel 2 and the secondary reactor containment vessel 3. It is sent to the main turbine 6 and the main condenser 7.
【０００４】前記主蒸気配管４には、原子炉格納容器２
の内側と外側に主蒸気隔離弁８，９を、またタービン建
屋５内には主蒸気止め弁10が介挿されていて、原子炉格
納容器２外における主蒸気配管４の破断等の事故発生に
際しては、事故信号11により前記主蒸気隔離弁８，９を
閉止して、蒸気とこれに含まれる放射性物質が原子炉格
納容器２外へ漏れることを防止している。A reactor containment vessel 2 is installed in the main steam pipe 4.
Main steam isolation valves 8 and 9 are installed inside and outside the main steam turbine, and a main steam stop valve 10 is inserted inside the turbine building 5 to cause an accident such as breakage of the main steam pipe 4 outside the reactor containment vessel 2. At this time, the main steam isolation valves 8 and 9 are closed by an accident signal 11 to prevent steam and radioactive substances contained therein from leaking out of the reactor containment vessel 2.
【０００５】従って、比較的発生頻度が高いと考えられ
る設計用最強地震（Ｓ1 ）発生時において、若しも原子
炉格納容器２の外側で主蒸気配管４が破断した場合に
は、この地震による共通原因によって同一サイト内の他
の主蒸気配管４も破断する可能性があると想定され、こ
れにより原子炉二次格納容器３内に放射性物質が漏洩す
ることになる。Therefore, when the strongest design earthquake (S1), which is considered to occur relatively frequently, occurs, if the main steam pipe 4 breaks outside the reactor containment vessel 2, the It is assumed that the other main steam pipes 4 in the same site may be broken due to the common cause, which causes the radioactive material to leak into the secondary reactor containment vessel 3.
【０００６】このために、主蒸気配管４は前記設計用最
強地震（Ｓ1 ）発生に際しても、原子炉格納容器２の内
側と外側に設けられた主蒸気隔離弁８，９から主蒸気止
め弁10までの主蒸気配管４は破断しないように十分に強
度を考慮した設計がされている。Therefore, the main steam pipe 4 is provided with main steam isolation valves 8 and 9 provided inside and outside the reactor containment vessel 2 to the main steam stop valve 10 even when the strongest design earthquake (S1) occurs. The main steam pipe 4 up to is designed with sufficient consideration of strength so as not to break.
【０００７】また、このような設計のもとでは、原子炉
格納容器２の内側で一次冷却材配管の破断事故が発生し
た場合にも、事故後長期間に亘って地震等によって原子
炉格納容器２の外側で主蒸気配管４が破断することはな
いと考えられたため、前記原子炉格納容器２から事故時
に漏洩した気体は、含まれる放射性物質が原子炉二次格
納容器３内に設置された非常用ガス処理系12によって捕
捉、除去された後に、主排気筒13より大気中へ放出され
る。このため従来は、特に主蒸気配管４において原子炉
二次格納容器３を隔離することの考慮はされていなかっ
た。Further, according to such a design, even if a breakage accident of the primary coolant piping occurs inside the reactor containment vessel 2, the reactor containment vessel is damaged by an earthquake or the like for a long period after the accident. Since it was considered that the main steam pipe 4 would not break outside of the reactor 2, the gas leaked from the reactor containment vessel 2 contained radioactive material contained in the reactor secondary containment vessel 3. After being captured and removed by the emergency gas processing system 12, it is released into the atmosphere from the main exhaust stack 13. Therefore, conventionally, the isolation of the secondary reactor containment vessel 3 particularly in the main steam pipe 4 has not been considered.
【０００８】[0008]
【発明が解決しようとする課題】従来の主蒸気配管４の
設計方針のもとでは、プラント建設の地盤の状態等の立
地条件によっては、過酷事故時における安全性を維持す
るための十分な主蒸気配管４の耐震性を確保するために
主蒸気配管４の構造強度をさらに増すとか、基礎をより
強固にする必要があるという課題があり、建設費用も高
騰する支障があった。Under the conventional design policy of the main steam pipe 4, depending on the location conditions such as the ground condition of the plant construction, the main steam pipe 4 has a sufficient main structure for maintaining safety in a severe accident. In order to ensure the earthquake resistance of the steam pipe 4, there is a problem that the structural strength of the main steam pipe 4 needs to be further increased or the foundation needs to be strengthened.
【０００９】本発明の目的とするところは、主蒸気配管
で原子炉二次格納容器の内外にタービン建屋を隔離する
隔離弁を設置して、地震に起因する主蒸気配管破損の過
酷事故に対してプラント建設の立地条件に対応した合理
的な主蒸気配管設計を可能とした主蒸気配管の原子炉二
次格納容器隔離装置を提供することにある。The object of the present invention is to install an isolation valve for isolating the turbine building inside and outside the reactor secondary containment vessel in the main steam pipe to prevent a severe accident of main steam pipe damage due to an earthquake. It is to provide a reactor secondary containment isolation device for main steam piping that enables a rational main steam piping design that meets the site conditions for plant construction.
【００１０】[0010]
【課題を解決するための手段】原子炉格納容器を内包す
ると共にタービン建屋と隣接した原子炉二次格納容器に
おいて、前記原子炉格納容器より原子炉二次格納容器と
タービン建屋を貫通して敷設した主蒸気配管に前記原子
炉格納容器の内側と外側に主蒸気隔離弁を、タービン建
屋の内側と外側に隔離弁を介挿設置すると共に、プラン
ト事故信号により前記主蒸気隔離弁を、プラント事故信
号と地震検出信号とにより前記隔離弁を閉止作動させる
ことを特徴とする。In a reactor secondary containment vessel which contains a reactor containment vessel and is adjacent to a turbine building, the reactor containment vessel is laid through the reactor secondary containment vessel and the turbine building. The main steam isolation valve was installed inside and outside the reactor containment vessel in the main steam pipe, and the isolation valve was installed inside and outside the turbine building. The isolation valve is closed by a signal and an earthquake detection signal.
【００１１】[0011]
【作用】地震発生により原子炉二次格納容器内において
主蒸気配管が破断すると、この事象は主蒸気流量高、主
蒸気管圧力低等のプラント事故信号、および主蒸気配管
が破断したことは当然設計用最強地震Ｓ1 相当以上規模
の地震であることから、設計用最強地震（Ｓ1 ）検出器
から地震検出信号が出力される。[Operation] When the main steam pipe breaks in the reactor secondary containment vessel due to the occurrence of an earthquake, this event is of course a plant accident signal such as high main steam flow rate, low main steam pipe pressure, and the main steam pipe was broken. Since the design strongest earthquake S1 has a magnitude equivalent to or larger than the design strongest earthquake S1, an earthquake detection signal is output from the design strongest earthquake (S1) detector.
【００１２】前記プラント事故信号により原子炉格納容
器の内側と外側に設置された主蒸気隔離弁が閉止作動す
ると共に、前記プラント事故信号と地震検出信号とによ
りタービン建屋内側と外側に設置された隔離弁が緊急閉
止する。The main steam isolation valve installed inside and outside the reactor containment vessel closes due to the plant accident signal, and the isolation installed inside and outside the turbine building by the plant accident signal and the earthquake detection signal. The valve closes urgently.
【００１３】これにより、原子炉格納容器内の原子炉圧
力容器からの主蒸気が原子炉二次格納容器に流れ込むこ
とが阻止され、また原子炉二次格納容器からタービン建
屋への蒸気に伴う放射能の漏洩が防止できる。なお、主
蒸気配管の破断口から原子炉二次格納容器内に漏洩した
蒸気に含まれる放射性物質は、非常用ガス処理系におい
て捕捉、除去される。As a result, the main steam from the reactor pressure vessel in the reactor containment vessel is prevented from flowing into the secondary reactor containment vessel, and the radiation from the secondary reactor containment vessel to the turbine building is emitted. Noh leakage can be prevented. The radioactive substances contained in the steam leaked into the secondary reactor containment vessel from the breakage port of the main steam pipe are captured and removed in the emergency gas treatment system.
【００１４】[0014]
【実施例】本発明の一実施例を図面を参照して説明す
る。なお、上記した従来技術と同じ構成部分については
同一符号を付して詳細な説明を省略する。図１は主蒸気
系統構図で、原子炉圧力容器１は原子炉格納容器２内に
格納されており、さらに原子炉格納容器２は原子炉二次
格納容器３に収容されている。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described with reference to the drawings. It should be noted that the same components as those in the above-described conventional technique are designated by the same reference numerals and detailed description thereof will be omitted. FIG. 1 is a main steam system composition in which a reactor pressure vessel 1 is stored in a reactor containment vessel 2, and the reactor containment vessel 2 is housed in a secondary reactor containment vessel 3.
【００１５】また前記原子炉圧力容器１から原子炉格納
容器２を貫通した主蒸気配管４は、原子炉二次格納容器
３内を十分に長く引き回されて、原子炉二次格納容器３
を貫通し、隣接したタービン建屋５へ導入されて主ター
ビン６に接続されている。Further, the main steam pipe 4 penetrating from the reactor pressure vessel 1 to the reactor containment vessel 2 is laid in the reactor secondary containment vessel 3 for a sufficiently long time so that the reactor secondary containment vessel 3
Is introduced into the adjacent turbine building 5 and is connected to the main turbine 6.
【００１６】なお、原子炉二次格納容器３において、原
子炉格納容器２との主蒸気配管４の貫通部には主蒸気隔
離弁８，９が、またタービン建屋５との貫通部には原子
炉二次格納容器の隔離弁14，15が、さらにタービン建屋
５内で主タービン６の入口近傍には主蒸気止め弁10が介
挿されていて、前記隔離弁14，15は耐震Ａクラス構造と
されている。In the secondary reactor containment vessel 3, main steam isolation valves 8 and 9 are provided in the penetration portion of the main steam pipe 4 with the reactor containment vessel 2, and the atom is provided in the penetration portion with the turbine building 5. Isolation valves 14 and 15 of the secondary reactor containment vessel and a main steam stop valve 10 are inserted in the turbine building 5 near the inlet of the main turbine 6, and the isolation valves 14 and 15 are seismic resistant A class structure. It is said that.
【００１７】前記主蒸気隔離弁８，９は、主蒸気流量
高、原子炉水位低、主蒸気管圧力低、主蒸気トンネル室
温度高および主復水器真空度信号等のプラント事故信号
11により閉止作動させるが、原子炉二次格納容器の隔離
弁14，15は、プラント事故信号11と設計用最強地震（Ｓ
1 ）検出装置16による地震検知信号の同時入力に際して
緊急閉止動作を開始するインターロックが設けられて構
成されている。次に上記構成による作用について説明す
る。The main steam isolation valves 8 and 9 are plant accident signals such as high main steam flow rate, low reactor water level, low main steam pipe pressure, high main steam tunnel room temperature, and main condenser vacuum degree signal.
11, but the isolation valves 14 and 15 of the secondary reactor containment vessel have the plant accident signal 11 and the strongest design earthquake (S
1) An interlock for starting an emergency closing operation when the earthquake detection signals are simultaneously input by the detection device 16 is provided. Next, the operation of the above configuration will be described.
【００１８】万一、地震発生により主蒸気配管４が、原
子炉二次格納容器３内において破断するという過酷事故
を想定した場合に、主蒸気配管４の原子炉格納容器２の
内側と外側に設置された主蒸気隔離弁８，９は、プラン
ト事故信号11の発生により閉止作動する。これにより、
原子炉圧力容器１からの主蒸気は原子炉格納容器２内の
主蒸気隔離弁８により遮断され、原子炉二次格納容器３
内に流入しない。In the unlikely event of a severe accident in which the main steam pipe 4 is broken in the secondary reactor containment vessel 3 due to the occurrence of an earthquake, the main steam pipe 4 is placed inside and outside the reactor containment vessel 2. The installed main steam isolation valves 8 and 9 are closed when the plant accident signal 11 is generated. This allows
Main steam from the reactor pressure vessel 1 is shut off by the main steam isolation valve 8 in the reactor containment vessel 2, and the secondary reactor containment vessel 3
Does not flow in.
【００１９】また原子炉二次格納容器３内に漏洩した蒸
気は主蒸気隔離弁９により原子炉格納容器２に逆流する
ことが阻止され、さらに前記プラント事故信号11と、設
計用最強地震（Ｓ1 ）検出装置16において地震発生を検
知して出力されるＳ1 地震検出信号17との同時入力によ
り、主蒸気配管４でタービン建屋５の貫通部に設置して
ある原子炉二次格納容器の隔離弁14，15は緊急閉止し
て、原子炉二次格納容器３内の放射能が破断口から主蒸
気配管４を介してタービン建屋５に流入することが防止
される。Further, the steam leaking into the secondary reactor containment vessel 3 is prevented from flowing back into the reactor containment vessel 2 by the main steam isolation valve 9, and further the plant accident signal 11 and the strongest design earthquake (S1) ) An isolation valve for the secondary reactor containment vessel installed at the penetration of the turbine building 5 in the main steam pipe 4 by simultaneous input with the S1 earthquake detection signal 17 output upon detection of an earthquake occurrence in the detector 16 14 and 15 are closed urgently to prevent the radioactivity in the secondary reactor containment vessel 3 from flowing into the turbine building 5 through the main steam pipe 4 from the breakage port.
【００２０】また主蒸気配管４の破断口から原子炉二次
格納容器３内に漏れた主蒸気による放射性物質は、従来
と同様に非常用ガス処理系12で捕捉、除去される。な
お、原子炉二次格納容器３内において、主蒸気配管４を
十分に長く引き回して敷設することにより、原子炉二次
格納容器の隔離弁14，15を緊急閉止した際に流れを阻止
された蒸気が主蒸気配管４や主蒸気隔離弁９、および隔
離弁14等に与える圧力上昇等の過渡現象を緩和して、主
蒸気配管４等の健全性を確保する。Further, the radioactive substance by the main steam leaked from the breakage opening of the main steam pipe 4 into the secondary reactor containment vessel 3 is captured and removed by the emergency gas treatment system 12 as in the conventional case. In the reactor secondary containment vessel 3, by laying the main steam pipe 4 sufficiently long, the flow was blocked when the isolation valves 14 and 15 of the reactor secondary containment vessel were urgently closed. The soundness of the main steam pipe 4 and the like is secured by mitigating transient phenomena such as pressure rise that steam gives to the main steam pipe 4, the main steam isolation valve 9, and the isolation valve 14 and the like.
【００２１】以上から、原子炉二次格納容器３と、原子
炉二次格納容器３における主蒸気配管４および主蒸気隔
離弁９、隔離弁14を含む主蒸気系の耐震レベルが向上す
ると共に、プラントの安全性、信頼性を確保して建設の
立地条件に対して合理的な主蒸気系の設計が容易に可能
となる。From the above, the seismic resistance level of the reactor secondary containment vessel 3 and the main steam system including the main steam piping 4 and the main steam isolation valve 9 and the isolation valve 14 in the reactor secondary containment vessel 3 is improved, and It is possible to easily design a main steam system that is rational to site conditions for construction while ensuring plant safety and reliability.
【００２２】また、他の実施例として、系統設備の構成
は図１に示した一実施例と同様であるが、図１では原子
炉二次格納容器の隔離弁14，15を耐震Ａクラスとしてい
るのに対して、原子炉二次格納容器３内の隔離弁15まで
の主蒸気配管４を耐震Ａクラスとすることにより、さら
に主蒸気系の耐震レベルが向上する。As another embodiment, the system equipment is similar in configuration to the one shown in FIG. 1, but in FIG. 1 the isolation valves 14 and 15 of the secondary reactor containment vessel are seismic class A. On the other hand, by making the main steam pipe 4 up to the isolation valve 15 in the secondary reactor containment vessel 3 seismic class A, the seismic resistance level of the main steam system is further improved.
【００２３】[0023]
【発明の効果】以上本発明によれば、過酷事故として想
定した地震に起因する主蒸気配管の破断事故に際して
も、原子炉建屋の原子炉二次格納容器とタービン建屋を
迅速に隔離できるので、放射性物質の漏洩とこれによる
放射能汚染が抑制することができ、主蒸気配管等の強度
および原子力発電プラントの設置条件の緩和と安全性、
信頼性を著しく向上する効果がある。As described above, according to the present invention, the reactor secondary containment vessel of the reactor building and the turbine building can be quickly separated even in the event of a main steam pipe breakage accident due to an earthquake assumed as a severe accident. Leakage of radioactive materials and the resulting radioactive contamination can be suppressed, the strength of main steam pipes and the relaxation of the installation conditions of nuclear power plants and safety,
It has the effect of significantly improving reliability.
【図１】本発明に係る一実施例の主蒸気系統構成図。FIG. 1 is a configuration diagram of a main steam system according to an embodiment of the present invention.
【図２】従来の主蒸気系統構成図。FIG. 2 is a conventional main steam system configuration diagram.
１…原子炉圧力容器、２…原子炉格納容器、３…原子炉
二次格納容器、４…主蒸気配管、５…主タービン、６…
主復水器、７…タービン建屋、８…主蒸気止め弁、９，
10…主蒸気隔離弁、11…事故信号、12…非常用ガス処理
系、13…主排気筒、14，15…原子炉二次格納容器の隔離
弁、16…設計用最強地震（Ｓ1 ）検出装置、17…Ｓ1 地
震検出信号。1 ... Reactor pressure vessel, 2 ... Reactor containment vessel, 3 ... Reactor secondary containment vessel, 4 ... Main steam pipe, 5 ... Main turbine, 6 ...
Main condenser, 7 ... Turbine building, 8 ... Main steam stop valve, 9,
10 ... Main steam isolation valve, 11 ... Accident signal, 12 ... Emergency gas processing system, 13 ... Main exhaust stack, 14, 15 ... Isolation valve for secondary reactor containment vessel, 16 ... Design strongest earthquake (S1) detection Equipment, 17 ... S1 Earthquake detection signal.
Claims (1)
ン建屋と隣接した原子炉二次格納容器において、前記原
子炉格納容器より原子炉二次格納容器とタービン建屋を
貫通して敷設した主蒸気配管に前記原子炉格納容器の内
外側に主蒸気隔離弁を、タービン建屋の内外側に隔離弁
を介挿して設置すると共に、プラント事故信号により前
記主蒸気隔離弁を、またプラント事故信号と地震検出信
号とにより前記隔離弁を閉止作動させることを特徴とす
る主蒸気配管の原子炉二次格納容器隔離装置。1. A main steam pipe that contains a reactor containment vessel and is laid down from the reactor containment vessel through the reactor secondary containment vessel and the turbine building in a reactor secondary containment vessel adjacent to the turbine building. The main steam isolation valve is installed inside and outside the reactor containment vessel, and the isolation valve is installed inside and outside the turbine building, and the main steam isolation valve is also detected by the plant accident signal, and the plant accident signal and earthquake detection are performed. A reactor secondary containment isolation device for main steam piping, characterized in that the isolation valve is closed by a signal.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP43A JPH06174890A (en) | 1992-12-09 | 1992-12-09 | Device for isolating main steam piping from secondary reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP43A JPH06174890A (en) | 1992-12-09 | 1992-12-09 | Device for isolating main steam piping from secondary reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH06174890A true JPH06174890A (en) | 1994-06-24 |
Family
ID=18209288
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP43A Pending JPH06174890A (en) | 1992-12-09 | 1992-12-09 | Device for isolating main steam piping from secondary reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH06174890A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2021109622A1 (en) * | 2019-12-04 | 2021-06-10 | 上海核工程研究设计院有限公司 | Integrated passive reactor system |
-
1992
- 1992-12-09 JP JP43A patent/JPH06174890A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2021109622A1 (en) * | 2019-12-04 | 2021-06-10 | 上海核工程研究设计院有限公司 | Integrated passive reactor system |
| GB2593389A (en) * | 2019-12-04 | 2021-09-22 | Shanghai Nuclear Eng Res & Design Inst Co Ltd | Integrated passive reactor system |
| US11894151B2 (en) | 2019-12-04 | 2024-02-06 | Shanghai Nuclear Engineering Research & Design Institute Co., Ltd. | Integrated reactor system having passive removal of residual heat |
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