JP2020008541A - Cooling system of nuclear reactor during accident - Google Patents
Cooling system of nuclear reactor during accident Download PDFInfo
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- JP2020008541A JP2020008541A JP2018138051A JP2018138051A JP2020008541A JP 2020008541 A JP2020008541 A JP 2020008541A JP 2018138051 A JP2018138051 A JP 2018138051A JP 2018138051 A JP2018138051 A JP 2018138051A JP 2020008541 A JP2020008541 A JP 2020008541A
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- 238000001816 cooling Methods 0.000 title claims abstract description 40
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 68
- 239000000498 cooling water Substances 0.000 claims description 8
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims 2
- 229910001873 dinitrogen Inorganic materials 0.000 claims 2
- 230000005855 radiation Effects 0.000 abstract 1
- 238000009835 boiling Methods 0.000 description 3
- 238000004880 explosion Methods 0.000 description 3
- 238000012423 maintenance Methods 0.000 description 3
- 238000013022 venting Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
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- 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
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
本発明は原子炉が事故時に過熱し爆発の危険性が出た時、稼働させる冷却装置(以下本文では冷却装置は本発明の冷却装置を意味する)に関する。 The present invention relates to a cooling device (hereinafter, the cooling device means the cooling device of the present invention) which is operated when a reactor is overheated in an accident and there is a danger of explosion.
原子炉の事故時、爆発を防ぐためベント(以下本文ではベントとは放射能を含んだ蒸気を空中に放出する事を意味する)により住民に大きな被害をもたらしていた。
原子炉の事故時に原子炉本体を保護する発明はベントすることを前提に考案されたものが多い。In the event of a nuclear reactor accident, vents (hereinafter, vents mean releasing radioactive steam into the air) to prevent explosions caused serious damage to residents.
Many inventions that protect the reactor body in the event of a nuclear reactor accident have been devised on the premise of venting.
従来の事故時のみ使用する冷却システムは事故対応のため、蒸気弁と給水弁を閉じた状態である事が条件として明記されず、冷却システムを稼働すれば、温度、圧力、水位、はそれに付随して低下するので別々に制御していなかった。
事故時、多くの保守要員を必要とし、その訓練と費用は多く、従来の事故の経過を見れば分かるように心理的な動揺により簡単な観察、判断も出来ない。The conventional cooling system used only in the event of an accident is not specified as a condition that the steam valve and the water supply valve are closed to respond to the accident.If the cooling system is operated, the temperature, pressure, water level, etc. And was not separately controlled.
In the event of an accident, many maintenance personnel are required, training and cost are high, and simple observations and judgments cannot be made due to psychological fluctuations as can be seen from the course of the conventional accident.
事故時、原子炉爆発の危険を避けるためにベントする事なく原子炉の温度、圧力、水位を常時の基準値に保つこと。
事故時原子炉の給水弁と蒸気弁を閉じた状態で連続運転できる冷却装置を開発すること、この時使用する電力、水、要員を少なくし、装置を小型、軽量、安価、安全にしさらに、事故修理完了後の運転再開の時間を短縮する事が課題である。In the event of an accident, maintain the reactor temperature, pressure, and water level at normal levels without venting to avoid the danger of a reactor explosion.
To develop a cooling system that can be operated continuously with the water supply valve and the steam valve of the reactor closed in the event of an accident, reduce the power, water, and personnel used at this time, make the system smaller, lighter, cheaper, safer, and The challenge is to reduce the time for resuming operation after the completion of accident repair.
原子炉には加圧型と沸騰水型があるが、原子炉を冷却することは同じなので本発明では沸騰水型原子炉について記述する。
事故時原子炉が過熱した場合、事故時のみ使用する冷却システムにより原子炉の温度を下げ、蒸気を水に戻して安全を確保する。
この場合全ての冷却装置の弁の負荷を少なくするために、冷却装置の内部圧力と原子炉の圧力を同じにし、弁を小型軽量安価にする。Although there are a pressurized reactor and a boiling water reactor, cooling of the reactor is the same, and therefore, the present invention describes a boiling water reactor.
If the reactor overheats in the event of an accident, the cooling system used only during the accident lowers the temperature of the reactor and returns steam to water to ensure safety.
In this case, in order to reduce the load on the valves of all the cooling devices, the internal pressure of the cooling devices and the pressure of the reactor are made the same, and the valves are made small, lightweight and inexpensive.
常時は冷却装置の冷却器の上部まで水を満たし、調整器には原子炉と同じ圧力の空気を蓄え、装置全体を原子炉の圧力と同じ圧力にして事故を待つ。
事故時、調整器の空気の量を空気圧ポンプと空気弁で制御して冷却器と原子炉の圧力が等しい状態で原子炉の水位を制御する。
原子炉の温度を冷却装置の冷却水の流量と循環ポンプの流量で制御する。
原子炉の水位が下がる場合は給水口から給水する。
このように原子炉の温度、水位、圧力、の目標値に対し制御する機器が決められているため従来のように冷却すれば全て低下するのでよしではない。Normally, water is filled up to the top of the cooler of the cooling system, the regulator stores air at the same pressure as the reactor, and the entire system is kept at the same pressure as the reactor and waits for an accident.
In the event of an accident, the amount of air in the regulator is controlled by a pneumatic pump and an air valve to control the reactor water level with the cooler and reactor pressure equal.
The temperature of the reactor is controlled by the flow rate of the cooling water of the cooling device and the flow rate of the circulation pump.
If the reactor water level drops, supply water from the water inlet.
As described above, since equipment for controlling the target values of the temperature, the water level, and the pressure of the nuclear reactor is determined, it is not good because if the cooling is performed as in the conventional case, the temperature decreases.
事故時原子炉の蒸気弁と給水弁を閉じ、発電機や復水器を停止した状態で原子炉の温度、圧力、水位を規定値に保ち原子炉を連続運転させる。
本発明の冷却装置は70気圧、400度の水を60気圧300度にする程度で、高温高圧の蒸気を低温の冷却水で冷却するため、冷却が容易で冷却器は小さくなり、冷却器の入口と出口の圧力差も1気圧以下のため非常用電源は従来の原子炉の給水機と復水器の0.5%程度である。At the time of the accident, the reactor is operated continuously with the reactor temperature, pressure and water level kept at specified values with the steam and water supply valves of the reactor closed and the generator and condenser stopped.
The cooling device of the present invention cools high-temperature, high-pressure steam with low-temperature cooling water at a pressure of 70 atm, 400 ° C water to 60 atm, 300 ° C. Since the pressure difference between the inlet and outlet is less than 1 atm, the emergency power supply is about 0.5% of the conventional reactor water supply and condenser.
事故対応の設備が小型安価でありボタン一つで自動的に稼働するため保守要員の必要は無く、安定までの時間は20秒程度であり、事故時の原子炉の温度、水位、圧力、の変動は無く、制御目的とこれを制御するための機器がはっきり関連付けされているので、従来のように冷却すれば全てが解決するような曖昧な制御ではない。
事故時のみ使用する、電力、水、は従来の0.5%程度であるが、念のため多少の予備を持つことは良い。
事故原因を修理後はボタン一つで20秒程度で運転再開出来る。The accident response equipment is small and inexpensive and operates automatically at the touch of a button, so there is no need for maintenance personnel, and the time until stabilization is about 20 seconds, and the temperature, water level, pressure, etc. Since there is no fluctuation and the control purpose and the device for controlling the control purpose are clearly linked, it is not an ambiguous control that can be solved by cooling all as conventionally.
The power and water used only in the event of an accident is about 0.5% of the conventional one, but it is good to have some reserve just in case.
After repairing the cause of the accident, operation can be resumed in about 20 seconds with the push of a button.
図1において原子炉1は既設の沸騰水型原子炉である。(加圧式でも同じである)
既設の蒸気弁と給水弁の原子炉側に、本発明の冷却装置の蒸気弁7と給水弁4を設置し、事故時既設の蒸気弁と給水弁を閉じた状態で本発明の冷却装置を運転する。In FIG. 1, a
The steam valve 7 and the
常時の待機状態では、給水口15から水を入れて冷却器17の上部まで水を満たし、調整器5に水13を10%空気11を90%程度入れた状態で、空気弁10と空気ポンプ9を操作して空気11の圧力を原子炉1の内部圧力と等しくする。
その後原子炉1の圧力と同じになるよう空気11の量を常時制御し続ける。
その後蒸気弁7と給水弁4と給水弁16と空気弁10を閉じ事故発生まで待機する。
事故時には、蒸気弁7給水弁4給水弁16空気弁10を開いて調整器5の空気11を抜き、冷却器17に原子炉1の蒸気2を入れて冷却し冷却器17の蒸気21を水22に変えて循環ポンプ6で原子炉1に給水する。
冷却器17の冷却管18に冷却水19、20または空気を通して蒸気21を冷却する。In the normal standby state, water is supplied from the
Thereafter, the amount of
After that, the steam valve 7, the
In the event of an accident, the steam valve 7, the
The
調整器5にセパレーター12を取り付け、調整器5の水13と空気11を分離する。
空気ポンプ9は調整器5に空気を送り、調整器5の空気11の圧力を原子炉1の圧力と同じにしながら、空気弁10と空気ポンプ9を制御して原子炉1の水位を調整する。
このように原子炉1の水位は調整器5の空気弁10と空気ポンプ9によって制御し、温度は冷却器17の冷却水19,20の量と循環ポンプ6の出力により制御し、圧力は温度に比例するので温度を制御すれば制御できるが、圧力だけ高く温度が低い状態で圧力だけ低くしたい場合には調整器の空気11を抜いて原子炉1の蒸気を冷却器17に入れ、循環ポンプ6の出力を上げる。The
The
Thus, the water level of the
これにより原子炉1の蒸気2の温度は常時の目標値より低下するが、圧力も低下する。
通常ではありえない事であるが、水が少なくなった時は給水口15から給水する。
通常ではありえない事であるが、水または蒸気が多すぎる場合は給水口15から放出する。
この場合も放出した水や蒸気を一時別のタンクに蓄えて冷却し蒸気等を大気に放出しない。As a result, the temperature of the
Although it is not usually possible, water is supplied from the
Although it is not usually possible, if there is too much water or steam, it is discharged from the
Also in this case, the released water and steam are temporarily stored in a separate tank and cooled, and the steam and the like are not released to the atmosphere.
図1の場合冷却器17は蒸気を外に冷却管18を内部に入れた場合であるが、逆に冷却水を外に蒸気管18を内部に入れても同じ動作になる。
事故時上記の設備を稼働するには、ボタン一つで自動的に行い保守要員を必要とせず、安定状態までの時間も20秒程度である。In the case of FIG. 1, the
In the event of an accident, the above equipment is operated automatically at the touch of a button, does not require maintenance personnel, and takes about 20 seconds to reach a stable state.
1 原子炉
2 蒸気
3 水
4 給水弁
5 調整器
6 循環ポンプ
7 蒸気弁
8 パイプ
9 空気ポンプ
10 空気弁
11 空気
12 セパレーター
13 水
14 パイプ
15 給水口
16 給水弁
17 冷却器
18 冷却管
19 冷却水
20 冷却水
21 蒸気
22 水DESCRIPTION OF
Claims (2)
2、本発明の冷却装置は蒸気または水を冷却する冷却器を持ち、この冷却器には常時上部まで水を入れること。
3、本発明の冷却装置は調整器を持ち、調整器に常時水を10%程度入れ、空気または窒素ガスを90%程度入れること。
4、正常運転中は本発明の冷却装置の全ての弁を閉じた状態で原子炉の圧力と本発明の冷却装置の内部圧力を等しくすること。
5、事故時原子炉の既設の蒸気弁と給水弁を閉じた状態で原子炉の温度を制御目標として冷却装置の冷却水の量と循環ポンプの水量を制御し、原子炉の圧力を制御目標として調整器の空気または窒素ガスの量を制御し、原子炉の水位を制御目標として冷却装置の給水口からの水の出し入れを制御すること。
ただし、事故が軽微な場合は原子炉の既設の蒸気弁と給水弁を開いて本発明の冷却装置を並列運転する場合もある。
上記1,2,3,4,5,の条件を同時に使用する原子炉の冷却装置
上記項目1,2,を同時に使用する原子炉の冷却装置1. The cooling device of the present invention has a steam valve and a water supply valve through which steam and water pass even when the steam valve and the water supply valve of the conventional reactor are closed.
2. The cooling device of the present invention has a cooler for cooling steam or water, and the cooler is always filled with water to the top.
3. The cooling device of the present invention has a regulator, and the regulator always contains about 10% of water and about 90% of air or nitrogen gas.
4. During normal operation, the pressure of the reactor and the internal pressure of the cooling device of the present invention should be equalized with all valves of the cooling device of the present invention closed.
5. In the event of an accident, with the existing steam valve and water supply valve of the reactor closed, control the amount of cooling water in the cooling system and the amount of water in the circulation pump with the temperature of the reactor as the control target, and control the pressure of the reactor. To control the amount of air or nitrogen gas in the regulator, and to control the water level in the reactor and control the flow of water in and out of the water inlet of the cooling system.
However, when the accident is minor, the existing steam valve and water supply valve of the reactor may be opened to operate the cooling device of the present invention in parallel.
Reactor cooling device using the above conditions 1, 2, 3, 4, 5 simultaneously The reactor cooling device using the above items 1, 2 simultaneously
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| JP2018138051A JP2020008541A (en) | 2018-07-04 | 2018-07-04 | Cooling system of nuclear reactor during accident |
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| JP2018138051A JP2020008541A (en) | 2018-07-04 | 2018-07-04 | Cooling system of nuclear reactor during accident |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111561690A (en) * | 2020-05-18 | 2020-08-21 | 中国核动力研究设计院 | Control method for dealing with pressure relief accidents of secondary sides of all steam generators |
| RU2763943C1 (en) * | 2021-05-28 | 2022-01-11 | Общество с ограниченной ответственностью "Корпорация Акционерной Компании "Электросевкавмонтаж" | Regulating device |
-
2018
- 2018-07-04 JP JP2018138051A patent/JP2020008541A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111561690A (en) * | 2020-05-18 | 2020-08-21 | 中国核动力研究设计院 | Control method for dealing with pressure relief accidents of secondary sides of all steam generators |
| CN111561690B (en) * | 2020-05-18 | 2021-12-21 | 中国核动力研究设计院 | Control method for dealing with pressure relief accidents of secondary sides of all steam generators |
| RU2763943C1 (en) * | 2021-05-28 | 2022-01-11 | Общество с ограниченной ответственностью "Корпорация Акционерной Компании "Электросевкавмонтаж" | Regulating device |
| WO2022250571A1 (en) * | 2021-05-28 | 2022-12-01 | Общество с ограниченной ответственностью "Корпорация Акционерной Компании "Электросевкавмонтаж" | Regulating device |
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