JPH06174885A - Auxiliary equipment cooling system equipment - Google Patents
Auxiliary equipment cooling system equipmentInfo
- Publication number
- JPH06174885A JPH06174885A JP43A JP32640692A JPH06174885A JP H06174885 A JPH06174885 A JP H06174885A JP 43 A JP43 A JP 43A JP 32640692 A JP32640692 A JP 32640692A JP H06174885 A JPH06174885 A JP H06174885A
- Authority
- JP
- Japan
- Prior art keywords
- cooler
- heavy water
- auxiliary
- steam discharge
- auxiliary equipment
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Control Of Temperature (AREA)
Abstract
(57)【要約】
【構成】循環ポンプ1,冷却水を冷却する熱交換器2,
閉ループ構成する配管9,プラント運転モードで補機冷
却水流量が異なり、直列接続構成となっている重水冷却
器3,蒸気放出プール冷却器6及びその他補機10から
構成されている。蒸気放出プール冷却器6の下流側に重
水冷却器3を接続する。プラント通常運転時は、蒸気放
出プール冷却器6で熱負荷がないため、重水冷却器3の
入口温度は他の補機10と同じ温度となり、重水温度一
定制御上何ら問題はない。
【効果】重水減速型原子炉のプラント通常運転時と異常
時で熱負荷が大きく変わらず、冷却水を供給する補機が
異なる補機冷却系設備において、同補機を直列に接続す
ることで、弁の切替え操作もなく、重水冷却器温度制御
弁バイパス弁及び蒸気放出プール冷却器電動弁が削除で
きる。
(57) [Summary] [Structure] Circulation pump 1, heat exchanger for cooling cooling water 2,
It is composed of a pipe 9 forming a closed loop, an auxiliary machine cooling water flow rate depending on a plant operation mode, and a heavy water cooler 3, a steam discharge pool cooler 6 and other auxiliary machines 10 which are connected in series. The heavy water cooler 3 is connected to the downstream side of the steam discharge pool cooler 6. During normal plant operation, there is no heat load on the steam discharge pool cooler 6, so the inlet temperature of the heavy water cooler 3 becomes the same as that of the other auxiliary equipment 10, and there is no problem in heavy water temperature constant control. [Effect] By connecting the auxiliary equipment in series in the auxiliary equipment cooling system equipment where the heat load does not change much between normal operation and abnormal operation of the heavy water deceleration reactor plant, and the auxiliary equipment that supplies cooling water is different. , The heavy water cooler temperature control valve bypass valve and the steam discharge pool cooler electric valve can be deleted without switching the valve.
Description
【0001】[0001]
【産業上の利用分野】本発明は、重水減速型原子炉のプ
ラント通常運転時と異常時に熱負荷がほぼ同等で、冷却
水を通水する補機が異なり、通水補機の切替え操作が必
要な補機冷却系設備で運転状態を変更する必要性をなく
したものであり、特に、プラント通常運転時と異常時で
弁の切替え操作をせず、プラント通常運転時と異常時に
通水が異なる補機を直列に接続することにより、系統の
運転状態を一定にした補機冷却系設備に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a heavy water deceleration-type nuclear reactor, in which the heat load is almost the same during normal operation and during abnormal times, the auxiliary equipment for passing cooling water is different, and the switching operation of the water passing auxiliary equipment is performed. This eliminates the need to change the operating state of the necessary auxiliary equipment cooling system equipment.In particular, the valve switching operation is not performed during normal plant operation and during abnormal conditions, and water flow during normal plant operation and during abnormal conditions The present invention relates to an auxiliary equipment cooling system facility in which the operating state of a system is made constant by connecting different auxiliary equipment in series.
【0002】[0002]
【従来の技術】重水減速型原子力プラントにおける補機
冷却系設備は、循環ポンプにより昇圧された冷却水を熱
交換器で冷却し、各補機へ通水し、各補機で熱交換され
た冷却水を循環ポンプへ戻す閉ループ構成になってい
る。各補機の中で、重水冷却器はプラント通常運転時カ
ランドリアタンク内に保有の減速材である重水の温度を
一定に保つための補機で、補機冷却系除熱量の約70%
を占める。プラントの異常時には、原子炉が停止される
ため、減速材である重水の発熱量は、炉出力の減少と共
に急激に減少することより、重水冷却器での必要除熱量
も約20%の10×106kcal/hに減少する。2. Description of the Related Art Auxiliary equipment cooling system equipment in a heavy water deceleration type nuclear power plant cools cooling water whose pressure has been boosted by a circulation pump with a heat exchanger, passes the water to each auxiliary equipment, and exchanges heat with each auxiliary equipment. It has a closed loop configuration that returns cooling water to the circulation pump. Among the auxiliary machines, the heavy water cooler is an auxiliary machine for keeping the temperature of heavy water, which is a moderator held in the calandria tank during the normal operation of the plant, constant, and is about 70% of the heat removal amount of the auxiliary system cooling system.
Occupy Since the reactor is shut down when the plant is abnormal, the calorific value of heavy water, which is a moderator, sharply decreases as the reactor output decreases, so the required heat removal amount in the heavy water cooler is about 20% of 10 ×. It is reduced to 10 6 kcal / h.
【0003】一方、蒸気放出プール冷却器は、プラント
通常運転時には、蒸気放出プールの水温上昇がないこと
から熱負荷はない。また、プラント異常時には、安全弁
等からの高温蒸気が蒸気放出プールに放出されるため、
蒸気放出プールの水温が上昇し、蒸気放出プール冷却器
での必要除熱量が増加し、プラント異常時における補機
冷却系除熱量の約30%を占める。On the other hand, the steam discharge pool cooler has no heat load because the water temperature of the steam discharge pool does not rise during normal plant operation. Also, when the plant is abnormal, high temperature steam from the safety valve etc. is released to the steam release pool,
The water temperature of the steam discharge pool rises, the required heat removal amount in the steam discharge pool cooler increases, and accounts for about 30% of the heat removal amount of the auxiliary equipment cooling system when the plant is abnormal.
【0004】このように、重水減速型原子力プラント
は、プラント通常運転時と異常時において補機冷却系設
備の熱負荷発生補機が異なる特徴がある。よって、補機
冷却系設備の循環流量を低減させる目的からプラント通
常運転時と異常時に通水補機の切替操作を必要としてい
る。As described above, the heavy water deceleration type nuclear power plant is characterized in that the heat load generating auxiliary equipment of the auxiliary equipment cooling system equipment is different during normal operation of the plant and during abnormal times. Therefore, in order to reduce the circulation flow rate of the auxiliary equipment cooling system, it is necessary to switch the water auxiliary equipment during normal operation of the plant and during abnormal operation.
【0005】すなわち、重水冷却器はプラント通常運転
時から異常時に切替る時、温度制御弁から温度制御弁バ
イパス弁に切替え補機冷却通水量を低下させ、蒸気放出
プール冷却器は、プラント通常運転時から異常時に切替
わる時、電動弁を全閉から全開にして補機冷却水の通水
を開始させている。That is, when the heavy water cooler is switched from the normal operation of the plant to an abnormal state, the temperature control valve is switched to the temperature control valve bypass valve to reduce the auxiliary cooling water flow amount, and the steam discharge pool cooler is used for the normal operation of the plant. When switching from time to time in an abnormal condition, the motor-operated valve is closed to full open to start the flow of auxiliary machine cooling water.
【0006】そのため、補機冷却系設備は、弁の開閉操
作を行うための運転モード検出信号及び弁の自動切替え
信号を必要としていた。Therefore, the auxiliary equipment cooling system facility requires an operation mode detection signal for opening and closing the valve and an automatic valve switching signal.
【0007】[0007]
【発明が解決しようとする課題】重水減速型原子炉の従
来技術を用いた補機冷却系設備の例を図2に示す。FIG. 2 shows an example of auxiliary equipment cooling system equipment using a conventional technique of a heavy water moderator reactor.
【0008】プラント通常運転時減速材である重水の温
度を一定に保つために設けている重水冷却器3は、カラ
ンドリアタンクへの重水入口温度が一定となる様冷却水
である補機冷却水の流量を温度制御弁4で約2300m
3/h に制御している。プラント異常時には、温度制御
弁4を全閉に、バイパス弁5を開のままにして、異常時
の必要流量600m3/h を確保している。また、プラ
ント異常時に高温の蒸気が流入することによる蒸気放出
プール8の水温上昇を抑制するために設けている蒸気放
出プール冷却器6は、プラント通常時は電動弁7を全閉
にしておき、プラント異常時には同弁を開にして約14
00m3/h を通水して、蒸気放出プール8の水温が7
0℃を超えない様にしている。The heavy water cooler 3 provided to keep the temperature of the heavy water which is the moderator during the normal operation of the plant is an auxiliary machine cooling water which is a cooling water so that the temperature of the heavy water inlet to the calandria tank becomes constant. Flow rate of about 2300m with temperature control valve 4
Controlled to 3 / h. When the plant is abnormal, the temperature control valve 4 is fully closed and the bypass valve 5 is left open to ensure the required flow rate of 600 m 3 / h at the time of abnormality. Further, in the steam discharge pool cooler 6 provided to suppress the rise in the water temperature of the steam discharge pool 8 due to the inflow of high-temperature steam at the time of plant abnormality, the motor-operated valve 7 is fully closed during normal plant operation, When the plant is abnormal, the valve is opened for about 14
The water temperature of the steam discharge pool 8 is 7 after passing 00 m 3 / h.
I try not to exceed 0 ℃.
【0009】よって、プラント通常運転時には重水冷却
器の必要流量2300m3/h 、異常時では、重水冷却
器の必要流量600m3/h と蒸気放出プール冷却器の
必要流量1400m3/h で補機冷却系設備としての通
水流量がほぼ同じであるため、プラント運転モード切替
信号による弁の開閉操作を必要としていた。[0009] Thus, the plant normally required flow rate 2300 m 3 / h of heavy water cooler during operation, the abnormal time, heavy water cooler required flow rate 600 meters 3 / h and the vapor discharge pool condenser required flow rate 1400 m 3 / h with accessory Since the flow rate of water as the cooling system equipment is almost the same, it was necessary to open and close the valve by the plant operation mode switching signal.
【0010】本発明の目的は、プラント運転モード変更
時にも弁の切替え操作の必要がない補機冷却系設備を提
供することにある。An object of the present invention is to provide an auxiliary equipment cooling system equipment which does not require valve switching operation even when the plant operation mode is changed.
【0011】[0011]
【課題を解決するための手段】上記目的は、プラント運
転モードの切替えにより、プラント通常運転時と異常時
の両状態の合計熱負荷が同じになる蒸気放出プール冷却
器と重水冷却器を直列に接続し、蒸気放出プール冷却器
を通水した後、重水冷却器に通水することで達成され
る。The above object is to connect a steam discharge pool cooler and a heavy water cooler in series so that the total heat load in both normal operation and abnormal operation of the plant becomes the same by switching the plant operation mode. It is achieved by connecting and passing water through the steam discharge pool cooler and then through the heavy water cooler.
【0012】[0012]
【作用】以下、本発明の基本的作用を図1により説明す
る。The basic operation of the present invention will be described below with reference to FIG.
【0013】図において、蒸気放出プール冷却器6と重
水冷却器3を直列に接続することにより、プラント通常
運転時は、熱負荷のない蒸気放出プール冷却器6を通水
後、重水冷却器3に通水されるため、蒸気放出プール冷
却器6出口温度は、従来技術の重水冷却器3入口温度と
同じになり、重水冷却器3における重水温度一定制御上
は何ら問題はない。In the figure, by connecting the steam discharge pool cooler 6 and the heavy water cooler 3 in series, during normal plant operation, the steam discharge pool cooler 6 having no heat load is passed through the heavy water cooler 3 after passing water. Therefore, the outlet temperature of the steam discharge pool cooler 6 becomes the same as the inlet temperature of the heavy water cooler 3 of the prior art, and there is no problem in the heavy water temperature constant control of the heavy water cooler 3.
【0014】また、プラント異常時には、蒸気放出プー
ル冷却器6で除熱後、重水冷却器3に通水されるが、重
水冷却器3はプラント通常運転時よりも除熱量が低下す
ること及び従来技術よりも補機冷却水流量が増えること
(プラント通常運転時と同じ流量)に伴い、蒸気放出プ
ール冷却器6除熱後の補機冷却水温度及び補機冷却水流
量でも充分重水冷却器の熱負荷は除熱できる。よって、
弁の切替え操作の必要なく、重水冷却器温度制御弁バイ
パス弁5も必要なくなる。When the plant is abnormal, the steam discharge pool cooler 6 removes heat, and then water is passed to the heavy water cooler 3. However, the heavy water cooler 3 has a lower heat removal amount than that during normal plant operation, and With the increase in the auxiliary cooling water flow rate (the same flow rate as during normal plant operation) compared to technology, the steam cooling pool cooler 6 temperature of the auxiliary cooling water after heat removal and the auxiliary cooling water flow rate are sufficient for the heavy water cooler. The heat load can be removed. Therefore,
The heavy water cooler temperature control valve bypass valve 5 is not necessary because the valve switching operation is not necessary.
【0015】[0015]
【実施例】以下、本発明の一実施例を図1により説明す
る。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIG.
【0016】図において、蒸気放出プール冷却器6と重
水冷却器3は他の補機と異なり直列に接続されている。In the figure, the steam discharge pool cooler 6 and the heavy water cooler 3 are connected in series unlike other auxiliary machines.
【0017】本実施例によれば、プラント通常運転時、
熱負荷のない蒸気放出プール冷却器6を通水後、重水冷
却器3に通水される。これより、蒸気放出プール冷却器
6の補機冷却水出口温度は、入口温度と変わらないた
め、重水冷却器3の補機冷却水入口温度は、従来技術の
入口温度と同じになることより、重水温度一定制御上何
ら問題はない。According to this embodiment, during normal plant operation,
After passing the steam discharge pool cooler 6 having no heat load, the water is passed to the heavy water cooler 3. From this, since the auxiliary machine cooling water outlet temperature of the steam discharge pool cooler 6 is not different from the inlet temperature, the auxiliary machine cooling water inlet temperature of the heavy water cooler 3 becomes the same as the conventional inlet temperature, There is no problem in constant control of heavy water temperature.
【0018】プラント異常時には、蒸気放出プール冷却
器6の必要UA値(伝熱面積×総括伝熱係数)約6×1
06kcal/h℃ 、補機冷却水の入口温度32℃及び補
機冷却水量2300m3/hとすると、交換熱量(Q)=
UA値×対数平均温度差(ΔTm)=流量(W)×比重(γ)
×比熱(Cp )×温度差(ΔT)の関係から除熱量は約1
6×106kcal/hとなるため、従来技術の除熱量15
×106kcal/hは確保可能である。また、この時の補
機冷却水出口温度は約40℃となり、この温度の補機冷
却水が重水冷却器3に供給されることになる。すなわ
ち、蒸気放出プール冷却器6の出口温度が重水冷却器の
入口温度となる。重水冷却器のプラント通常運転時の必
要交換熱量は、減速材である重水の温度を一定に保つた
め、約42×106kcal/h必要であるが、異常時には
炉出力の低下により減速材である重水での発熱量が約1
0×106kcal/hに減少する。このため、重水冷却器
の補機冷却水入口温度が通常時の32℃から異常時にお
いて約40℃に上昇しても、補機冷却水流量がプラント
通常時と同じ2300m3/h のため、重水冷却器の必
要UA値3×106kcal/h℃とすると、除熱量は20
×106kcal/hとなり、必要除熱量の10×106kca
l/hは、充分除熱可能である。When the plant is abnormal, the required UA value of the steam discharge pool cooler 6 (heat transfer area x overall heat transfer coefficient) is about 6 x 1
0 6 kcal / h ° C., inlet temperature of auxiliary machine cooling water 32 ° C., and amount of auxiliary machine cooling water 2300 m 3 / h, heat exchange amount (Q) =
UA value × logarithmic mean temperature difference (ΔT m ) = flow rate (W) × specific gravity (γ)
The heat removal amount is about 1 due to the relationship of x specific heat ( Cp ) x temperature difference (ΔT)
Since it is 6 × 10 6 kcal / h, the heat removal amount of the conventional technology is 15
× 10 6 kcal / h can be secured. At this time, the outlet temperature of the auxiliary machine cooling water is about 40 ° C., and the auxiliary machine cooling water at this temperature is supplied to the heavy water cooler 3. That is, the outlet temperature of the steam discharge pool cooler 6 becomes the inlet temperature of the heavy water cooler. The required amount of heat exchange for the heavy water cooler during normal plant operation is approximately 42 × 10 6 kcal / h in order to keep the temperature of the heavy water, which is the moderator, constant. About 1 calorific value of heavy water
It is reduced to 0 × 10 6 kcal / h. Therefore, even if the auxiliary cooling water inlet temperature of the heavy water cooler rises from 32 ° C in normal times to about 40 ° C in abnormal times, the auxiliary cooling water flow rate is 2300 m 3 / h, which is the same as in normal plant operation. When the required UA value of the heavy water cooler is 3 × 10 6 kcal / h ° C, the heat removal amount is 20
× 10 6 kcal / h, which is the required heat removal amount of 10 × 10 6 kca
1 / h can sufficiently remove heat.
【0019】以上、蒸気放出プール冷却器と重水冷却器
を直列通水とすることにより、プラント通常運転時、異
常時共弁の開閉操作は不要となるため、従来技術でプラ
ント異常時に使用する予定のバイパス弁5は不要とな
り、温度制御弁4のみで運転可能となる。さらに、蒸気
放出プール冷却器6の電動弁7も不要となり、メンテナ
ンス用の手動弁のみの設置でプラント運転モード切替に
対する弁操作上の必要性がなくなる。As described above, by connecting the steam discharge pool cooler and the heavy water cooler in series, it is not necessary to open / close the common valve at the time of normal plant operation. The bypass valve 5 is unnecessary, and the temperature control valve 4 alone can be operated. Further, the electric valve 7 of the steam discharge pool cooler 6 is also unnecessary, and the need for valve operation for switching the plant operation mode is eliminated by installing only a manual valve for maintenance.
【0020】本実施例では、蒸気放出プール冷却器の下
流側に重水冷却器を接続した例を示しているが、その接
続順番を逆にしても本効果は望める。In this embodiment, an example in which a heavy water cooler is connected on the downstream side of the steam discharge pool cooler is shown, but this effect can be expected even if the connection order is reversed.
【0021】[0021]
【発明の効果】本発明によればプラント状態の変化によ
っても補機冷却系設備の熱負荷が大きく変わらなく、通
水する補機が異なる補機冷却系設備において、運転状態
の変化に伴う弁の切替え操作もなく、余分な弁も削除可
能となり、運転が簡略化される。According to the present invention, the heat load of the auxiliary equipment cooling system equipment does not change significantly even when the plant state changes, and in the auxiliary equipment cooling system equipment through which water is passed, the valve accompanying the change of the operating state The operation can be simplified because the extra valve can be deleted without switching operation.
【図1】本発明の補機冷却系設備一実施例を示すブロッ
ク図。FIG. 1 is a block diagram showing an embodiment of an accessory cooling system facility of the present invention.
【図2】従来技術を用いた補機冷却系設備のブロック
図。FIG. 2 is a block diagram of auxiliary equipment cooling system equipment using a conventional technique.
1…循環ポンプ、2…熱交換器、3…重水冷却器、4…
重水冷却器温度制御弁、5…温度制御弁バイパス弁、6
…蒸気放出プール冷却器、7…電動弁、8…蒸気放出プ
ール、9…配管、10…補機。1 ... Circulation pump, 2 ... Heat exchanger, 3 ... Heavy water cooler, 4 ...
Heavy water cooler temperature control valve, 5 ... Temperature control valve bypass valve, 6
... Steam release pool cooler, 7 ... Motorized valve, 8 ... Steam release pool, 9 ... Piping, 10 ... Auxiliary equipment.
Claims (1)
異常時に熱負荷がほぼ同等で、冷却水を通水する補機が
異なり通水補機の切替え操作が必要な補機冷却系設備に
おいて、前記補機を直列に接続し、通常運転時も異常時
にも通水させる補機を変更させる必要がないことを特徴
とする補機冷却系設備。1. A cooling system facility for a heavy water deceleration type reactor in which the heat load is almost the same when the plant is in normal operation and when it is abnormal, and the auxiliary device for passing the cooling water is different and the switching operation of the water passing auxiliary device is required. 2. The auxiliary equipment cooling system facility, wherein the auxiliary equipment is connected in series, and it is not necessary to change the auxiliary equipment through which water is passed during normal operation and abnormal conditions.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP43A JPH06174885A (en) | 1992-12-07 | 1992-12-07 | Auxiliary equipment cooling system equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP43A JPH06174885A (en) | 1992-12-07 | 1992-12-07 | Auxiliary equipment cooling system equipment |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH06174885A true JPH06174885A (en) | 1994-06-24 |
Family
ID=18187440
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP43A Pending JPH06174885A (en) | 1992-12-07 | 1992-12-07 | Auxiliary equipment cooling system equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH06174885A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107941037A (en) * | 2017-12-21 | 2018-04-20 | 中国电力工程顾问集团西北电力设计院有限公司 | A kind of subsidiary engine cooling water system of high-low-position arrangement |
| CN107941036A (en) * | 2017-12-21 | 2018-04-20 | 中国电力工程顾问集团西北电力设计院有限公司 | A kind of subsidiary engine cooling water system of high-order arrangement |
| CN113157016A (en) * | 2021-03-23 | 2021-07-23 | 北京无线电计量测试研究所 | Incubator for atomic clock and use method |
-
1992
- 1992-12-07 JP JP43A patent/JPH06174885A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107941037A (en) * | 2017-12-21 | 2018-04-20 | 中国电力工程顾问集团西北电力设计院有限公司 | A kind of subsidiary engine cooling water system of high-low-position arrangement |
| CN107941036A (en) * | 2017-12-21 | 2018-04-20 | 中国电力工程顾问集团西北电力设计院有限公司 | A kind of subsidiary engine cooling water system of high-order arrangement |
| CN107941037B (en) * | 2017-12-21 | 2023-08-18 | 中国电力工程顾问集团西北电力设计院有限公司 | Auxiliary engine cooling water system with high-low arrangement |
| CN107941036B (en) * | 2017-12-21 | 2023-08-22 | 中国电力工程顾问集团西北电力设计院有限公司 | Auxiliary engine cooling water system arranged at high position |
| CN113157016A (en) * | 2021-03-23 | 2021-07-23 | 北京无线电计量测试研究所 | Incubator for atomic clock and use method |
| CN113157016B (en) * | 2021-03-23 | 2022-08-23 | 北京无线电计量测试研究所 | Incubator for atomic clock and use method |
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