JPH0432798A - Nuclear reactor pressure reduction maintaining device - Google Patents
Nuclear reactor pressure reduction maintaining deviceInfo
- Publication number
- JPH0432798A JPH0432798A JP2138365A JP13836590A JPH0432798A JP H0432798 A JPH0432798 A JP H0432798A JP 2138365 A JP2138365 A JP 2138365A JP 13836590 A JP13836590 A JP 13836590A JP H0432798 A JPH0432798 A JP H0432798A
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- nuclear reactor
- reactor
- breakage
- reactor pressure
- 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
- 238000002955 isolation Methods 0.000 claims abstract description 11
- 238000012423 maintenance Methods 0.000 claims description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 7
- 239000000155 melt Substances 0.000 abstract 1
- 230000008018 melting Effects 0.000 abstract 1
- 238000002844 melting Methods 0.000 abstract 1
- 239000012808 vapor phase Substances 0.000 abstract 1
- 239000007789 gas Substances 0.000 description 5
- 238000001816 cooling Methods 0.000 description 3
- 230000035515 penetration Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000000889 atomisation Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000002035 prolonged effect Effects 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
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用いられる原子炉減圧維持装置
に関する。Detailed Description of the Invention [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor depressurization maintenance device used in a nuclear power plant.
（従来の技術）
従来、原子力発電所では原子炉圧力容器に逃し弁あるい
は安全弁（以下総称してＳＲ弁と呼ぶ）が設けられてい
る。そして、原子炉圧力容器の圧力が過大になった場合
に、これらが自動作動し、原子炉圧力を一定値（数十気
圧）以下に保つことができる。また、沸騰水型原子炉（
以下ＢＷＲと呼ぶ）では非當炉心冷却系の一つとしてＡ
ＤＳ（自動減圧系）か設けられており、原子炉圧力を数
気圧まで強制的に自動減圧することが可能である。しか
し前記ＳＲ弁は原子炉を高圧状態で−・定値以下に保つ
ことしかできない。また、ＡＤＳは事故時に原子炉格納
容器の内圧が高いと、弁を閉鎖してしまうため、−旦は
原子炉を低下状態に導くことはできるが、原子炉格納容
器内圧が」１昇して来ると、再び、原子炉圧力もＪ：ｆ
／シてしまう。(Prior Art) Conventionally, in nuclear power plants, a relief valve or safety valve (hereinafter collectively referred to as an SR valve) is provided in a reactor pressure vessel. When the pressure in the reactor pressure vessel becomes excessive, these systems automatically operate to maintain the reactor pressure below a certain value (several tens of atmospheres). In addition, boiling water reactors (
(hereinafter referred to as BWR), A is used as one of the non-core cooling systems.
A DS (automatic depressurization system) is installed, and it is possible to forcibly and automatically reduce the reactor pressure to several atmospheres. However, the SR valve can only maintain the reactor at a high pressure below a certain value. Additionally, if the internal pressure of the reactor containment vessel is high in the event of an accident, ADS closes the valve, so although it is possible to bring the reactor to a low state for a few days, the internal pressure of the reactor containment vessel will rise by 1. When it comes, the reactor pressure is also J:f again.
/ I'm dying.
（発明か解決しようとする課題）
設計基準事故を超えて炉心が損傷する事故（以下５ＣＤ
Ａと呼ぶ）が発生すると、この事故進展を途中で停止し
得なかった場合には炉心は溶融し、原子炉圧力容器下部
に落下し、さらには原子炉圧力容器下部を溶融貫通し原
子炉格納容器内に溶融炉心が放出される。その際原子炉
圧力容器が数十気圧という高圧にあれば、溶融炉心は原
子炉格納容器内に高圧放出され、いたる所に飛散してし
まうおそれがある。また、原子炉圧力容器が溶融貫通す
る際に原子炉圧力容器内に大きな、かつ、急激な圧力上
昇が発生する。この圧力スパイクにより原子炉格納容器
が破損すると、大量の放射能が環境に放出されるおそれ
がある。仮にその圧力スパイクによって原子炉格納容器
が破損しなくても、飛散した溶融炉心が原子炉格納容器
内の酸素と急激な酸化反応を起こし、その発熱によって
、原子炉格納容器が直接加熱されて破損に至るおそれも
ある。(Invention or problem to be solved) Accident in which the reactor core is damaged beyond the design basis accident (hereinafter referred to as 5CD)
If the accident progress cannot be stopped midway, the reactor core will melt and fall into the lower part of the reactor pressure vessel, and even penetrate the lower part of the reactor pressure vessel, causing the reactor containment. A molten core is released into the vessel. At that time, if the reactor pressure vessel is at a high pressure of several tens of atmospheres, there is a risk that the molten core will be released under high pressure into the reactor containment vessel and be scattered everywhere. Further, when the reactor pressure vessel is melted and penetrated, a large and rapid pressure rise occurs within the reactor pressure vessel. If the reactor containment vessel were to rupture due to this pressure spike, large amounts of radioactivity could be released into the environment. Even if the reactor containment vessel is not damaged by the pressure spike, the scattered molten core will cause a rapid oxidation reaction with the oxygen inside the reactor containment vessel, and the heat generated will directly heat the reactor containment vessel and cause damage. There is also a risk that this may lead to
このように５ＣＤＡ時に原子炉圧力容器が高圧であるこ
とは極めて好ましくない結果をもたらす。As described above, the high pressure in the reactor pressure vessel at the time of 5CDA brings about extremely unfavorable results.
しかし、前述のように現状のＳＲ弁やＡＤＳでは５ＣＤ
Ａ時に原子炉圧力を低圧に維持することは困難な場合も
ある。そこで５ＣＤＡ時にも確実に原子炉圧力を低圧に
維持できる原子炉減圧維持装置を提供する。However, as mentioned above, the current SR valve and ADS have a 5CD
It may be difficult to maintain the reactor pressure at low pressure during A. Therefore, a nuclear reactor depressurization maintenance device is provided that can reliably maintain the reactor pressure at a low pressure even during 5CDA.
［発明の構成］
（課題を解決するための手段）
原子炉圧力容器の気相部に連結し、原子炉格納容器内に
導かれた配管と、この配管上に直流電源もしくは気体駆
動の隔離弁を設置する。[Structure of the invention] (Means for solving the problem) A pipe connected to the gas phase part of the reactor pressure vessel and led into the reactor containment vessel, and a DC power supply or gas-driven isolation valve on this pipe. Set up.
（作 用）
ＳＣＤＡの発生は何らかの理由により、原子炉の水位が
低下し、炉心露出が長期化した場合に起こる。このよう
に、原子炉の水位が低下する最大の要因としては全交流
電源喪失事象がある。(Effect) SCDA occurs when, for some reason, the water level in the reactor drops and the core is exposed for a prolonged period of time. As described above, the biggest factor causing the water level in the reactor to drop is the event of total AC power loss.
全交流電源喪失が発生すると、交流電源を使用している
非常用炉心冷却系は全て使用不可能となる。原子炉への
注水はタービン駆動の原子炉隔離時冷却系（ＲＣＩＣと
呼ぶ）によってのみ可能であるが、数時間で制御用に使
用しているステーションバッテリーか枯渇するとＲＣＩ
Ｃも停止してしまう。その結果、原子炉水位が低下し、
炉心損傷が発生するおそれかある。これをこのまま放置
すると原子炉圧力容器の溶融貫通が高圧状態で発生して
しまうので、ＡＤＳによって原子炉圧力を事前に低圧状
態に導くことが望ましい。その具体的方法としては、Ａ
ＤＳの作動信号の変更とか制御バッテリーのＡＤＳ専用
化等が別途検討されている。これにより一旦原子炉圧力
は低下するが、原子炉燃料から放出され続ける崩塘熱に
より、原子炉格納容器の内圧が上昇すると、ＡＤＳは再
び閉鎖してしまう。ＡＤＳか閉鎖すると１時間程度で原
子炉圧力は再び数十気圧にまで上Ｒしてしまう。そこで
このようなことを防止するため、ＡＤＳが作動し、原子
炉圧力が一旦低下した時点で、本発明による原子炉減圧
維持装置の隔離弁を専用の直流電源もしくは気体供給系
によって開状態にし、原子炉内で発生した水蒸気等を原
子炉格納容器内に放出する。その後、原子炉格納容器の
内圧が上昇し、ＡＤＳは閉鎖する。しかし、本発明によ
る原子炉減圧維持装置がすでに作動しているため、原子
炉圧力が百び」１昇することはない。If a total AC power loss occurs, all emergency core cooling systems using AC power become unusable. Water can only be injected into the reactor using a turbine-driven Reactor Isolation Cooling System (RCIC), but if the station battery used for control is depleted within a few hours, the RCI
C also stops. As a result, the reactor water level drops,
There is a risk of core damage. If this is left as it is, melt penetration of the reactor pressure vessel will occur in a high pressure state, so it is desirable to bring the reactor pressure to a low pressure state in advance by ADS. The specific method is A.
Changes to the DS operating signal and the use of a control battery exclusively for ADS are being considered separately. As a result, the reactor pressure temporarily decreases, but as the internal pressure of the reactor containment vessel increases due to the collapse heat that continues to be released from the reactor fuel, the ADS closes again. If the ADS were shut down, the reactor pressure would rise again to several tens of atmospheres in about an hour. Therefore, in order to prevent this, when the ADS is activated and the reactor pressure once drops, the isolation valve of the reactor depressurization maintenance device according to the present invention is opened by a dedicated DC power supply or gas supply system. Release water vapor generated inside the reactor into the reactor containment vessel. After that, the internal pressure of the reactor containment vessel increases and the ADS closes. However, since the reactor pressure reduction maintenance device according to the present invention is already in operation, the reactor pressure will not rise by 100%.
このようにして原子炉圧力容器の溶融貫通が発生する時
点にあっても、原子炉圧力容器は低圧に維持されるため
溶融炉心が原子炉格納容器内に飛び散って直接加熱破損
や圧カスバイクによる原子炉格納容器の過圧破損が生じ
ることを防止できる。In this way, even at the point where melt penetration of the reactor pressure vessel occurs, the reactor pressure vessel is maintained at a low pressure, so the molten reactor core is scattered into the reactor containment vessel, resulting in direct heating damage and atomic atomization due to pressure build-up. It is possible to prevent overpressure damage to the reactor containment vessel.
（実施例） 以下本発明の一実施例を第１図を参照して説明る。(Example) An embodiment of the present invention will be described below with reference to FIG.
第１図において原子炉圧力容器１の気相部である原子炉
圧力容器上蓋部６に接続されたベント配管２は原子炉格
納容器（図示せず）内のサンプ３中に導かれる。通常時
このベント配管２を閉鎖するために隔離弁４を設置する
。隔離弁４は信頼性向１−のため多重に設置してもよい
。また、隔Ｋｔ弁４は専用の直流（ＤＣ）電源５によっ
て駆動する。In FIG. 1, a vent pipe 2 connected to a reactor pressure vessel upper cover 6, which is a gas phase portion of a reactor pressure vessel 1, is guided into a sump 3 in a reactor containment vessel (not shown). An isolation valve 4 is installed to close this vent pipe 2 under normal conditions. The isolation valves 4 may be installed in multiple numbers because of the reliability property 1-. Further, the distance Kt valve 4 is driven by a dedicated direct current (DC) power source 5.
このＤＣ電源５は常設であるか可搬式であるかのいずれ
てあってもよい。また、隔離弁４は気体作動弁、駆動源
は気体供給系であってもよい。This DC power source 5 may be either permanently installed or portable. Further, the isolation valve 4 may be a gas-operated valve, and the driving source may be a gas supply system.
［発明の効果］
本発明による原子炉減圧維１ｊＩ装置によって原子炉圧
力容器の溶融貫通が発生する時点にあっても、原子炉圧
力容器は低圧に維持されるため、溶融炉心が原子炉格納
容器内に飛び散って直接加熱破損や圧力スパイクによる
原子炉格納容器の過圧破損が生じることを防止できる。[Effects of the Invention] The reactor pressure vessel is maintained at a low pressure even at the time when melt penetration of the reactor pressure vessel occurs by the reactor depressurization fiber 1jI device according to the present invention, so that the molten core is kept in the reactor containment vessel. This can prevent direct heating damage caused by splashing inside the reactor, as well as overpressure damage to the reactor containment vessel due to pressure spikes.
第１図は本発明の一実施例を示す原子炉減圧維持装置の
系統概要図である。
１・・・原子炉圧力容器
２・・・ベント配管
３・・・サンプ
５・・・直流電源
４・・・隔離弁FIG. 1 is a system schematic diagram of a nuclear reactor depressurization maintenance device showing one embodiment of the present invention. 1... Reactor pressure vessel 2... Vent piping 3... Sump 5... DC power supply 4... Isolation valve
Claims (1)
かれた配管と、この配管に設置された直流電源によって
作動する隔離弁とから構成される原子炉減圧維持装置。A nuclear reactor depressurization maintenance device consisting of a pipe connected to the gas phase part of the reactor pressure vessel and led into the reactor pressure vessel, and an isolation valve installed in this pipe and operated by a DC power source.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2138365A JPH0432798A (en) | 1990-05-30 | 1990-05-30 | Nuclear reactor pressure reduction maintaining device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2138365A JPH0432798A (en) | 1990-05-30 | 1990-05-30 | Nuclear reactor pressure reduction maintaining device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0432798A true JPH0432798A (en) | 1992-02-04 |
Family
ID=15220229
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2138365A Pending JPH0432798A (en) | 1990-05-30 | 1990-05-30 | Nuclear reactor pressure reduction maintaining device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0432798A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2010236878A (en) * | 2009-03-30 | 2010-10-21 | Toshiba Corp | Boiling water reactor |
| CN106601312A (en) * | 2017-01-19 | 2017-04-26 | 清华大学天津高端装备研究院 | ADS (accelerator driven sub-critical system) integrated reactor top structure and nuclear power generation equipment |
-
1990
- 1990-05-30 JP JP2138365A patent/JPH0432798A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2010236878A (en) * | 2009-03-30 | 2010-10-21 | Toshiba Corp | Boiling water reactor |
| US20100290576A1 (en) * | 2009-03-30 | 2010-11-18 | Kabushiki Kaisha Toshiba | Boiling water reactor |
| US8744034B2 (en) | 2009-03-30 | 2014-06-03 | Kabushiki Kaisha Toshiba | Boiling water reactor |
| CN106601312A (en) * | 2017-01-19 | 2017-04-26 | 清华大学天津高端装备研究院 | ADS (accelerator driven sub-critical system) integrated reactor top structure and nuclear power generation equipment |
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