JPH0222354B2 - - Google Patents
Info
- Publication number
- JPH0222354B2 JPH0222354B2 JP56046475A JP4647581A JPH0222354B2 JP H0222354 B2 JPH0222354 B2 JP H0222354B2 JP 56046475 A JP56046475 A JP 56046475A JP 4647581 A JP4647581 A JP 4647581A JP H0222354 B2 JPH0222354 B2 JP H0222354B2
- Authority
- JP
- Japan
- Prior art keywords
- pump
- cooling system
- seawater
- cooling
- residual heat
- 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
Links
- 238000001816 cooling Methods 0.000 claims description 63
- 239000013535 sea water Substances 0.000 claims description 29
- 238000011144 upstream manufacturing Methods 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 13
- 239000000498 cooling water Substances 0.000 description 11
- 230000007774 longterm Effects 0.000 description 7
- 230000001629 suppression Effects 0.000 description 6
- 238000009835 boiling Methods 0.000 description 4
- 238000002955 isolation Methods 0.000 description 3
- 238000009833 condensation Methods 0.000 description 2
- 230000005494 condensation Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000007921 spray Substances 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000000034 method 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)
Description
【発明の詳細な説明】
本発明は、沸とう水型原子炉の残留熱除去系の
機器冷却系、および海水冷却系に関するものであ
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an equipment cooling system for a residual heat removal system of a boiling water nuclear reactor and a seawater cooling system.
従来、沸とう水型原子炉で使用される残留熱除
去系、およびその機器冷却系と海水冷却系につい
て第１図を用いて説明する。残留熱除去系には、
以下に示す５つの使用形態（モード）がある。 A residual heat removal system conventionally used in a boiling water nuclear reactor, its equipment cooling system, and a seawater cooling system will be explained with reference to FIG. The residual heat removal system includes
There are five usage forms (modes) shown below.
(1) 低圧注水モード
圧力抑制プール１３の水が直接原子炉１２に送
られ炉水位が確保される。(1) Low-pressure water injection mode Water from the pressure suppression pool 13 is sent directly to the reactor 12 to ensure the reactor water level.
(2) 格納容器スプレーモード
圧力抑制プール１３の水が格納容器１９内にス
プレーされ、格納容器１９内の熱が除去される。(2) Containment Vessel Spray Mode Water from the pressure suppression pool 13 is sprayed into the containment vessel 19, and heat within the containment vessel 19 is removed.
(3) プーレ水冷却モード
圧力抑制プール１３内の水温が上昇した時に、
プール水は残留熱除去系ポンプ１４Ａ，１４Ｂに
より熱交換器１１Ａ，１１Ｂに送られ、そこで冷
却され圧力抑制プール１３に戻される。(3) Poole water cooling mode When the water temperature in the pressure suppression pool 13 rises,
The pool water is sent to the heat exchangers 11A, 11B by the residual heat removal system pumps 14A, 14B, where it is cooled and returned to the pressure suppression pool 13.
(4) 蒸気凝縮モード
原子炉１２内で発生した蒸気は、配管１５を介
して熱交換器１１Ａ，１１Ｂに送られ、そこで凝
縮され、凝縮した水は原子炉隔離時ポンプ１６に
より原子炉１２に戻される。(4) Steam condensation mode Steam generated in the reactor 12 is sent to the heat exchangers 11A and 11B via piping 15, where it is condensed, and the condensed water is sent to the reactor 12 by the reactor isolation pump 16. be returned.
(5) 停止時冷却モード
原子炉１２内の冷却水は配管１７を介し、残留
熱除去系ポンプ１４Ａ，１４Ｂにより、熱交換器
１１Ａ，１１Ｂに送られ、冷却され配管１８によ
り原子炉１２に戻される。(5) Cooling mode during shutdown Cooling water in the reactor 12 is sent to the heat exchangers 11A and 11B via the piping 17 by the residual heat removal system pumps 14A and 14B, cooled, and returned to the reactor 12 through the piping 18. It will be done.
上記５モードのうち、(3)，(4)および(5)の３モー
ドは熱交換器１１Ａ，１１Ｂを介して原子炉１２
および圧力抑制プール１３の熱を外部へ除去する
ことにより、長期の冷却を達成するためのモード
である。 Of the above five modes, the three modes (3), (4) and (5) are
This is a mode for achieving long-term cooling by removing heat from the pressure suppression pool 13 to the outside.
機器冷却系および海水冷却系は、それぞれＡと
Ｂの２系統あり、熱交換器１１Ａと１１Ｂの熱を
外部へ除去するために設けられている。機器冷却
系はそれぞれ50％容量の機器冷却系ポンプ２１
Ａ，２１Ｃと２１Ｂ，２１Ｄより成り、50％容量
の熱交換器２２Ａ，２２Ｃと２２Ｂ，２２Ｄを介
して、熱を海水冷却系へ移す。海水冷却系はそれ
ぞれ50％容量の海水冷却系ポンプ３１Ａ，３１Ｃ
と３１Ｂ，３１Ｄより成り熱を海水３２へ移行す
る。 There are two equipment cooling systems and a seawater cooling system, A and B, respectively, which are provided to remove heat from the heat exchangers 11A and 11B to the outside. The equipment cooling system is equipped with equipment cooling system pumps 21 each with a capacity of 50%.
It consists of A, 21C, 21B, and 21D, and heat is transferred to the seawater cooling system through 50% capacity heat exchangers 22A, 22C, 22B, and 22D. The seawater cooling system uses seawater cooling system pumps 31A and 31C, each with a capacity of 50%.
, 31B, and 31D, and transfers heat to seawater 32.
残留熱除去系のポンプのうち、原子炉隔離時ポ
ンプ１６はタービンにより駆動する。またＡ系の
ポンプは非常用デイーゼル発電機４１Ａが、Ｂ系
のポンプは非常用デイーゼル発電機４１Ｂが配線
されている。 Among the pumps in the residual heat removal system, the reactor isolation pump 16 is driven by a turbine. Further, the A-system pump is wired with an emergency diesel generator 41A, and the B-system pump is wired with an emergency diesel generator 41B.
事故発生時には、長期の冷却を確保するために
上記した残留熱除去系の３モードを切り換えて用
いるが、この３モード間で共通に使用する必要が
ある機器冷却系ポンプ、海水冷却系ポンプおよび
非常用デイーゼル発電機の信頼性向上を図ること
は事故時の残留熱除去系の信頼性をより向上し、
長期の冷却達成を容易にする上で有効な方法であ
る。 In the event of an accident, the three modes of the residual heat removal system described above are switched and used to ensure long-term cooling, but the equipment cooling system pump, seawater cooling system pump, and emergency Improving the reliability of diesel generators will further improve the reliability of the residual heat removal system in the event of an accident.
This is an effective method for easily achieving long-term cooling.
本発明の目的は、残留熱除去系の非常用デイー
ゼル発電機、および機器冷却系と海水冷却系のポ
ンプの信頼性を向上させ、事故時の残留熱除去系
の信頼性を向上し、長期の冷却を容易にする機器
冷却系および海水冷却系を提供することにある。 The purpose of the present invention is to improve the reliability of the emergency diesel generator of the residual heat removal system and the pumps of the equipment cooling system and the seawater cooling system, to improve the reliability of the residual heat removal system in the event of an accident, and to improve the reliability of the residual heat removal system in the event of an accident. An object of the present invention is to provide an equipment cooling system and a seawater cooling system that facilitate cooling.
本発明の残留熱除去系の機器冷却系および海水
冷却系は、独立の２系統より構成される残留熱除
去系の機器冷却系および海水冷却系において、前
記機器冷却系のポンプの上流側を結合する第１の
配管および前記機器冷却系のポンプの下流側を結
合する第２の配管、前記海水冷却系のポンプの下
流側を結合する第３の配管、前記第１の配管と前
記第２の配管との間および海水と前記第３の配管
との間にそれぞれ接続され、前記２系統とは独立
の非常用デイゼル発電機を有する第３の系統のポ
ンプ、および前記第１の配管に設けられ前記２系
統のポンプの上流側への流入を阻止する逆止弁と
前記第２および前記第３の配管に設けられ前記２
系統のポンプの下流からの流入を阻止する逆止弁
により構成されることを特徴とするものである。 The equipment cooling system and seawater cooling system of the residual heat removal system of the present invention are composed of two independent systems, and the upstream side of the pump of the equipment cooling system is connected to the equipment cooling system and the seawater cooling system of the residual heat removal system. a second pipe that connects the downstream side of the pump of the equipment cooling system with a first pipe that connects the downstream side of the pump of the equipment cooling system; a third pipe that connects the downstream side of the pump of the seawater cooling system; a third system pump connected between the piping and between the seawater and the third piping, and having an emergency diesel generator independent of the two systems; and a third system pump provided in the first piping. A check valve that prevents inflow to the upstream side of the two pumps; and a check valve that is provided in the second and third pipes, and
It is characterized by comprising a check valve that prevents inflow from downstream of the pump in the system.
以下、本発明を実施例を参照して詳細に説明す
る。第２図は本発明になる機器冷却系および海水
冷却系の構成図である。機器冷却系ポンプ２１
Ａ，２１Ｂ，２１Ｃ，２１Ｄの上流側を配管２４
により結合し、下流側を配管２５により結合し、
その配管を接続する機器冷却系ポンプ２１Ｅ，２
１Ｆを増設する。この機器冷却系ポンプ２１Ｅ，
２１Ｆには、従来法で用いられている非常用デイ
ーゼル発電機４１Ａ，４１Ｂとは異なる非常用デ
イーゼル発電機４１Ｃが配線されている。この非
常用デイーゼル発電機４１Ｃとしては高圧炉心ス
プレー系の非常用デイーゼル発電機を流用するこ
とができる。なお、逆止弁２３Ａ，２３Ｂ，２３
Ｃ，２３Ｄは２系統を隔離し、それぞれの系統の
故障の影響を受けないようにするために設けてあ
る。 Hereinafter, the present invention will be explained in detail with reference to Examples. FIG. 2 is a configuration diagram of an equipment cooling system and a seawater cooling system according to the present invention. Equipment cooling system pump 21
Piping 24 on the upstream side of A, 21B, 21C, 21D
and the downstream side is connected by piping 25,
Equipment cooling system pumps 21E, 2 to which the piping is connected
1F will be added. This equipment cooling system pump 21E,
An emergency diesel generator 41C, which is different from the emergency diesel generators 41A and 41B used in the conventional method, is wired to 21F. As this emergency diesel generator 41C, a high pressure core spray type emergency diesel generator can be used. In addition, check valves 23A, 23B, 23
C and 23D are provided to isolate the two systems and prevent them from being affected by failures in either system.
海水冷却系も同様にして海水冷却系ポンプ３１
Ｅ，３１Ｆ、海水冷却系ポンプ３１Ａ，３１Ｂ，
３１Ｃ，３１Ｄの下流側を結合する配管３３、お
よび逆止弁３４Ａ，３４Ｂが増設してある。 Similarly, the seawater cooling system is connected to the seawater cooling system pump 31.
E, 31F, seawater cooling system pump 31A, 31B,
A piping 33 connecting the downstream sides of 31C and 31D, and check valves 34A and 34B are added.
上記の構成によると、機器冷却系ポンプ２１
Ｅ，２１Ｆが待機ポンプとして２配管２４，２５
を介してＡ，Ｂの両系統に接続しているため、両
系統のそれぞれに対して冗長性を構成することに
なる。例えばＡ系のポンプ２１Ａもしくは２１Ｃ
がトリツプすれば、ポンプ２１Ｅもしくは２１Ｆ
が立ち上がり、配管２４，２５を介してＡ系へ冷
却水が供給され、Ａ系統は100％の除熱能力を保
つことができる。この時Ｂ系統は、逆止弁２３
Ｂ，２３Ｄがあるため、Ｂ系統の冷却水がＡ系統
へ流入することはなく、100％の除熱能力を保つ
ことができる。例えば、通常運転時には、ポンプ
上流側では、逆止弁２３Ｂにより、Ａ系統からＢ
系統への冷却水の流入を、又逆に逆止弁２３Ａに
より、Ｂ系統からＡ系統への冷却水の流入を防い
でいる。ポンプ下流側では、逆止弁２３Ｃによ
り、Ａ系統からＢ系統への冷却水の流入を、又逆
に逆止弁２３Ｄにより、Ｂ系統からＡ系統への冷
却水の流入を防いでいる。次に、Ａ系統のポンプ
２１Ａ及び２１Ｃが故障した場合を考えると、ポ
ンプ上流側では、通常運転時と同様の原理で冷却
水の流入を防いでいるが、ポンプ下流側では、逆
止弁２３Ａを介して流入したＡ系統の冷却水が逆
止弁２３Ｄを介してＢ系統へ流入する可能性が考
えられる。しかし、この場合、Ｂ系統はポンプ２
１Ｂ及びポンプ２１Ｄが稼動しており、配管長の
相違による差圧のためこのような逆止弁２３Ｄを
介してＢ系統へ流入することはほとんど生じな
い。また、逆止弁２３Ｂを介して流入したＢ系統
の冷却水が逆止弁２３Ｃを介してＡ系統へ流入す
る可能性も、配管長の相違による差圧のためほと
んど生じない。従つて、Ａ系統のポンプの故障時
においても、Ａ系統の冷却水はポンプ２１Ｅ，２
１Ｆを用いた流路を介し、Ｂ系統の冷却水はポン
プ２１Ｂ，２１Ｄを用いた流路を介して流れるた
め、Ａ系統の故障の影響がＢ系統へ及ぶことは実
質的には無い。待機ポンプとして設けられている
海水冷却系ポンプ３１Ｅ，３１Ｆについても同様
である。このためそれぞれの系統のポンプの不信
頼度は約1/20に低減する。電源喪失時の非常用デ
イーゼル発電機についても同様の理由により不信
頼度は約1/4に低減する。このため事故時に、機
器冷却系および海水冷却系の故障のために残留熱
除去系が使用不能となる事態は減小し、残留熱除
去系の有効な利用が可能となる。特に電源喪失時
はタービン駆動のポンプを用いる蒸気凝縮モード
は、機器冷却系、および海水冷却系に対して非常
用デイーゼル発電機が強化されるため有効に利用
できるようになる。従つて事故時の長期の冷却の
達成が容易となる。例えば、給水流量喪失時の長
期の冷却達成失敗確率は１／104に、電源喪失時
の長期の冷却達成失敗確率は１／102となる。 According to the above configuration, the equipment cooling system pump 21
E, 21F is a standby pump with 2 pipes 24, 25
Since it is connected to both systems A and B via, redundancy is configured for each of both systems. For example, A-system pump 21A or 21C
If it trips, pump 21E or 21F
starts, cooling water is supplied to the A system via the pipes 24 and 25, and the A system can maintain 100% heat removal capacity. At this time, the B system is connected to the check valve 23.
Since there are B and 23D, the cooling water of the B system does not flow into the A system, and 100% heat removal capacity can be maintained. For example, during normal operation, on the upstream side of the pump, the check valve 23B prevents the flow from the A system to the B system.
The check valve 23A prevents cooling water from flowing into the system, and conversely from flowing from the B system to the A system. On the downstream side of the pump, a check valve 23C prevents cooling water from flowing from the A system to the B system, and a check valve 23D prevents cooling water from flowing from the B system to the A system. Next, considering the case where pumps 21A and 21C of system A break down, on the upstream side of the pump, the inflow of cooling water is prevented using the same principle as during normal operation, but on the downstream side of the pump, check valve 23A There is a possibility that the cooling water of the A system that has flowed in through the check valve 23D may flow into the B system through the check valve 23D. However, in this case, the B system is pump 2.
1B and the pump 21D are in operation, and because of the pressure difference due to the difference in pipe length, there is almost no flow into the B system via the check valve 23D. Further, there is almost no possibility that the cooling water of the B system that has flowed in through the check valve 23B will flow into the A system through the check valve 23C because of the pressure difference due to the difference in pipe length. Therefore, even if the A system pump fails, the A system cooling water is supplied to the pumps 21E and 21E.
Since the cooling water of the B system flows through the flow path using the 1F and through the flow path using the pumps 21B and 21D, there is virtually no effect of a failure in the A system on the B system. The same applies to the seawater cooling system pumps 31E and 31F, which are provided as standby pumps. Therefore, the unreliability of the pumps in each system is reduced to about 1/20. For the same reason, the unreliability of emergency diesel generators when power is lost is reduced to about 1/4. Therefore, in the event of an accident, the situation where the residual heat removal system becomes unusable due to a failure of the equipment cooling system or the seawater cooling system is reduced, and the residual heat removal system can be used effectively. Particularly in the event of a power loss, the steam condensation mode using a turbine-driven pump can be effectively utilized as emergency diesel generators are reinforced for equipment cooling systems and seawater cooling systems. Therefore, it is easier to achieve long-term cooling in the event of an accident. For example, the probability of failure to achieve long-term cooling when the water supply flow rate is lost is 1/10 4 , and the probability of failure to achieve long-term cooling when power is lost is 1/10 2 .
以上説明したごとく、本発明によれば機器冷却
系および海水冷却系の信頼性が向上するため、残
留熱除去系の有効な利用が可能となり、事故時の
長期冷却達成の信頼性が向上する。このため沸と
う水型原子力プラントの安全性が向上する。 As explained above, according to the present invention, the reliability of the equipment cooling system and the seawater cooling system is improved, so the residual heat removal system can be used effectively, and the reliability of achieving long-term cooling in the event of an accident is improved. This improves the safety of boiling water nuclear power plants.
第１図は従来の沸とう水型原子炉の残留熱除去
系、機器冷却系、および海水冷却系の構成図、第
２図は本発明になる残留熱除去系の機器冷却系お
よび海水冷却系の構成図である。
１１Ａ，１１Ｂ……熱交換器、１２……原子
炉、１３……圧力抑制プール、１４Ａ，１４Ｂ…
…残留熱除去系ポンプ、１６……原子炉隔離時ポ
ンプ、１９……格納容器、２１Ａ，２１Ｂ，２１
Ｃ，２１Ｄ……機器冷却系ポンプ、３２……海
水。
Figure 1 is a configuration diagram of the residual heat removal system, equipment cooling system, and seawater cooling system of a conventional boiling water reactor, and Figure 2 is the equipment cooling system and seawater cooling system of the residual heat removal system of the present invention. FIG. 11A, 11B... Heat exchanger, 12... Nuclear reactor, 13... Pressure suppression pool, 14A, 14B...
... Residual heat removal system pump, 16 ... Reactor isolation pump, 19 ... Containment vessel, 21A, 21B, 21
C, 21D... equipment cooling system pump, 32... seawater.
Claims (1)
機器冷却系および海水冷却系において、前記機器
冷却系のポンプの上流側を結合する第１の配管お
よび前記機器冷却系のポンプの下流側を結合する
第２の配管、前記海水冷却系のポンプの下流側を
結合する第３の配管、前記第１の配管と前記第２
の配管との間および海水と前記第３の配管との間
にそれぞれ接続され、前記２系統とは独立の非常
用デイゼル発電機を有する第３の系統のポンプ、
および前記第１の配管に設けられ前記２系統のポ
ンプの上流側への流入を阻止する逆止弁と前記第
２および前記第３の配管に設けられ前記２系統の
ポンプの下流からの流入を阻止する逆止弁により
構成されることを特徴とする残留熱除去系の機器
冷却系および海水冷却系。1 In an equipment cooling system and a seawater cooling system of a residual heat removal system consisting of two independent systems, a first pipe connecting the upstream side of the pump of the equipment cooling system and a downstream side of the pump of the equipment cooling system. a second pipe to be connected, a third pipe to connect the downstream side of the pump of the seawater cooling system, and the first pipe and the second pipe to be connected to each other;
a third system pump having an emergency diesel generator connected between the piping and the seawater and the third piping, and independent from the two systems;
and a check valve provided in the first pipe to prevent inflow from the upstream side of the two pump systems; and a check valve provided in the second and third pipes to prevent inflow from the downstream side of the two pump systems. A residual heat removal equipment cooling system and a seawater cooling system characterized by comprising a check valve that prevents the residual heat from being removed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56046475A JPS57161592A (en) | 1981-03-31 | 1981-03-31 | Equipment cooling system and sea water cooling system in residual heat removal system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56046475A JPS57161592A (en) | 1981-03-31 | 1981-03-31 | Equipment cooling system and sea water cooling system in residual heat removal system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57161592A JPS57161592A (en) | 1982-10-05 |
| JPH0222354B2 true JPH0222354B2 (en) | 1990-05-18 |
Family
ID=12748214
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56046475A Granted JPS57161592A (en) | 1981-03-31 | 1981-03-31 | Equipment cooling system and sea water cooling system in residual heat removal system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57161592A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6029696A (en) * | 1983-07-28 | 1985-02-15 | 株式会社東芝 | Cooling device for nuclear power plant |
| JP4903303B2 (en) * | 2000-12-07 | 2012-03-28 | ユニバーサル造船株式会社 | Hull structure |
| US6928132B2 (en) * | 2001-12-19 | 2005-08-09 | General Electric Company | Methods and apparatus for operating a system |
-
1981
- 1981-03-31 JP JP56046475A patent/JPS57161592A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57161592A (en) | 1982-10-05 |
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