JPH02170097A - Nuclear reactor cooling adjustment device - Google Patents
Nuclear reactor cooling adjustment deviceInfo
- Publication number
- JPH02170097A JPH02170097A JP63325119A JP32511988A JPH02170097A JP H02170097 A JPH02170097 A JP H02170097A JP 63325119 A JP63325119 A JP 63325119A JP 32511988 A JP32511988 A JP 32511988A JP H02170097 A JPH02170097 A JP H02170097A
- Authority
- JP
- Japan
- Prior art keywords
- cooling
- reactor
- panel
- nuclear reactor
- pipes
- 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.)
- Granted
Links
- 238000001816 cooling Methods 0.000 title claims abstract description 96
- 239000000498 cooling water Substances 0.000 claims abstract description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 230000007423 decrease Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000011835 investigation 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、原子炉冷却調整装置に係り、特に原子炉圧力
容器からの放熱量を原子炉の運転状態に応じて冷却する
ことのできる原子炉冷却調整装置に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a nuclear reactor cooling adjustment device, and in particular to a nuclear reactor cooling adjustment device that can cool the amount of heat released from a reactor pressure vessel according to the operating state of the reactor. The present invention relates to a furnace cooling adjustment device.
従来の原子炉冷却調整装置においては、第３図及び第４
図に示すように構成されていた。図において、原子炉の
炉心１は炉心支持構造物２を介して原子炉圧力容器３内
に固定されている。この原子炉圧力容器３は炉室コンク
リート４で形成された炉室内に設置されており、この炉
室コンクリート４の内壁に沿って複数本の冷却管５から
なる冷却パネル６が設けられている。これらの冷却管５
は入口ヘッダ（冷却水管）７及び出口ヘッダ（冷却水管
）８に接続されており、常時入口ヘッダ７から冷却水を
注入し出口へラダ８から排出して冷却管５内に冷却水を
流し、原子炉圧力容器３を輻射伝熱９により冷却してい
る（日本原子力研究所納 多目的高温ガス実験炉システ
ム調整（２）調査報告書昭和６１年６月参照）。このよ
うに構成された原子炉冷却調整装置は、原子炉強制冷却
喪失時において原子炉スクラム後の崩壊熱を除熱し、原
子炉圧力容器３及び炉心１の温度上昇を許容温度以下に
抑える目的で設置されており、その除熱性能は炉心１の
出力の約３％以」二の放熱量を冷却する能力を有してい
る。In the conventional reactor cooling adjustment system, Fig. 3 and Fig. 4
It was configured as shown in the figure. In the figure, a reactor core 1 is fixed within a reactor pressure vessel 3 via a core support structure 2. As shown in FIG. This reactor pressure vessel 3 is installed in a reactor chamber formed of reactor chamber concrete 4, and a cooling panel 6 consisting of a plurality of cooling pipes 5 is provided along the inner wall of this reactor chamber concrete 4. These cooling pipes 5
is connected to an inlet header (cooling water pipe) 7 and an outlet header (cooling water pipe) 8, and cooling water is constantly injected from the inlet header 7 and discharged from the ladder 8 to the outlet to flow into the cooling pipe 5. The reactor pressure vessel 3 is cooled by radiation heat transfer 9 (see Japan Atomic Energy Research Institute Multipurpose High Temperature Gas Experimental Reactor System Adjustment (2) Investigation Report June 1986). The reactor cooling adjustment device configured in this way is designed to remove the decay heat after the reactor scram when forced reactor cooling is lost, and to suppress the temperature rise in the reactor pressure vessel 3 and the reactor core 1 to below the allowable temperature. The heat removal performance is capable of cooling the amount of heat released by approximately 3% or more of the output of the reactor core 1.
従来の原子炉冷却調整装置にあっては、通常運転時にお
いて除熱量が大きすぎ、原子炉熱効率が低下するととも
に、原子炉出口温度も制約されるという問題があった。Conventional nuclear reactor cooling adjustment devices have problems in that the amount of heat removed during normal operation is too large, reducing reactor thermal efficiency and restricting the reactor outlet temperature.
本発明の目的は、原子炉圧力容器からの放熱量を原子炉
の運転状態に応じて冷却することができる原子炉冷却調
整装置を提供することにある。An object of the present invention is to provide a reactor cooling adjustment device that can cool the amount of heat released from a reactor pressure vessel according to the operating state of the reactor.
前記の目的を達成するため、本発明に係る原子炉冷却調
整装置は、原子炉圧力容器の外周に設けられた冷却パネ
ルにより原子炉の冷却調整を行なう原子炉冷却調整装置
において、原子炉圧力容器と冷却パネルとの間に複数本
の冷却管からなる補助冷却パネルを設けるとともに、補
助冷却パネルを複数の区分に分割し、それぞれの区分に
冷却水管を接続するように構成されている。In order to achieve the above object, a reactor cooling adjustment device according to the present invention is a reactor cooling adjustment device that adjusts cooling of a nuclear reactor using a cooling panel provided on the outer periphery of a reactor pressure vessel. An auxiliary cooling panel consisting of a plurality of cooling pipes is provided between the auxiliary cooling panel and the cooling panel, and the auxiliary cooling panel is divided into a plurality of sections, and a cooling water pipe is connected to each section.
本発明によれば、原子炉冷却調整装置に補助冷却パネル
を設けて複数の区分に分割したため、冷却水を通水する
区分を選択することによって、補助冷却パネルを介して
除熱量が調節される。したがって通常運転時における原
子炉圧力容器からの除熱量が調節され、同時に炉室コン
クリートの冷却も従来の冷却パネルにより冷却される。According to the present invention, since the reactor cooling adjustment device is provided with an auxiliary cooling panel and divided into a plurality of sections, the amount of heat removed can be adjusted via the auxiliary cooling panel by selecting the section through which cooling water is passed. . Therefore, the amount of heat removed from the reactor pressure vessel during normal operation is adjusted, and at the same time, the reactor chamber concrete is cooled by the conventional cooling panel.
また原子炉強制冷却喪失時は、この補助冷却パネルの全
区分の全冷却管に冷却水が通水される。In addition, when forced reactor cooling is lost, cooling water is passed through all cooling pipes in all sections of this auxiliary cooling panel.
本発明の一実施例を第１図及び第２図を参照しながら説
明する。An embodiment of the present invention will be described with reference to FIGS. 1 and 2.
第１図及び第２図に示すように、原子炉圧力容器３の外
周に設けられた冷却パネル６により原子炉１の放熱量を
冷却する原子炉冷却調整装置において、原子炉圧力容器
３と冷却パネル６との間に複数本の冷却管１０からなる
補助冷却パネル１１を設けるとともに、この補助冷却パ
ネル１１を複数の区分に分割し、それぞれの区分に冷却
水管を接続した構成である。As shown in FIGS. 1 and 2, in a reactor cooling adjustment device that cools the amount of heat released from the reactor 1 using a cooling panel 6 provided on the outer periphery of the reactor pressure vessel 3, the reactor pressure vessel 3 and cooling An auxiliary cooling panel 11 consisting of a plurality of cooling pipes 10 is provided between the panel 6 and the auxiliary cooling panel 11 is divided into a plurality of sections, and a cooling water pipe is connected to each section.
冷却管１０は複数本づつ、例えば５本づつを１区分とし
、それぞれの区分の１番目の冷却管１゜の入口側は共通
の第１の入口ヘッダ（冷却水管）１２に接続されている
。同様にそれぞれの区分の２番目乃至５番目の冷却管１
０はそれぞれ第２乃至第５の入口ヘッダ１３．１４．１
５．１６に接続されている。またこれらの冷却管１０の
出口側も同様に図示せぬ５本の出口ヘッダ（冷却水管）
に接続されており、入１コヘツダ１２乃至１６と出口ヘ
ッダにはそれぞれ人口弁１７乃至２１及び出口弁２２乃
至２６が設けられている。また従来の冷却パネル６の入
口へラダ７及び出口へラダ８にはそれぞれ人口弁２７．
２８が設けられている。A plurality of cooling pipes 10, for example, five cooling pipes, are arranged in one section, and the inlet side of the first cooling pipe 1° of each section is connected to a common first inlet header (cooling water pipe) 12. Similarly, the second to fifth cooling pipes 1 of each section
0 are the second to fifth inlet headers 13.14.1, respectively.
5.16 is connected. Furthermore, the outlet sides of these cooling pipes 10 are similarly connected to five outlet headers (cooling water pipes) (not shown).
The inlet headers 12 to 16 and the outlet header are respectively provided with artificial valves 17 to 21 and outlet valves 22 to 26. In addition, the conventional cooling panel 6 has a population valve 27 at the inlet ladder 7 and the outlet ladder 8, respectively.
28 are provided.
そして入口弁２７．１７乃至２１は並列に配設されてお
り、配管２９を介して循環ポンプ３０の吐出側に接続さ
れている。同様に出口弁２８．２２乃至２６も並列に配
設されており、配管３１．３２を介して順次冷却器３３
及び循環ポンプ３０の入口側に接続されている。そして
５組に分割された補助冷却パネル１１のそれぞれに接続
された入口弁１７乃至２１と出口弁２２乃至２６を開閉
することにより、通水される冷却管」０の本数を調節し
、補助冷却パネル１１の温度を制御できるようになって
いる。The inlet valves 27.17 to 21 are arranged in parallel and connected to the discharge side of the circulation pump 30 via a pipe 29. Similarly, the outlet valves 28, 22 to 26 are arranged in parallel and are connected to the cooler 33 in turn via the piping 31, 32.
and is connected to the inlet side of the circulation pump 30. By opening and closing the inlet valves 17 to 21 and outlet valves 22 to 26 connected to each of the auxiliary cooling panels 11 divided into five groups, the number of cooling pipes through which water is passed is adjusted, and the auxiliary cooling The temperature of the panel 11 can be controlled.
次に本実施例の作用を説明する。原子炉圧力容器３から
の輻射伝熱による除熱量（冷却すべき放熱量）の調整は
、輻射受熱面となる補助冷却パネル１１の冷却管１０の
うち冷却水を通水する区分を選択し、冷却管１０の本数
を増減することにより、冷却温度を変化させて達成でき
る。従って、原子炉通常運転時においては、この補助冷
却パネル１］の温度を、冷却管１０の制限した本数に通
水することにより調節し、原子炉の運転状態に合致した
除熱量を選択して適正な２００℃乃至３００℃に維持す
ることができる。このとき炉室コンクリ−１−４の温度
は従来の冷却パネル６により６５℃以下に保つことがで
きる。例えば、補助冷却パネル１１の入口弁１７．１８
及び出口弁２２．２３を開いて、補助冷却パネル１１の
２１５の冷却管で冷却するようにする。このとき運転状
態によっては補助冷却パネル１］−の１１５．３１５．
４１５の冷却管で冷却してもよい。Next, the operation of this embodiment will be explained. To adjust the amount of heat removed by radiation heat transfer from the reactor pressure vessel 3 (the amount of heat released to be cooled), select the section through which cooling water will flow among the cooling pipes 10 of the auxiliary cooling panel 11, which will serve as the radiation heat receiving surface. This can be achieved by changing the cooling temperature by increasing or decreasing the number of cooling pipes 10. Therefore, during normal reactor operation, the temperature of this auxiliary cooling panel 1 is adjusted by passing water through a limited number of cooling pipes 10, and the amount of heat removed that matches the operating state of the reactor is selected. It can be maintained at an appropriate temperature of 200°C to 300°C. At this time, the temperature of the concrete furnace chamber 1-4 can be maintained at 65 DEG C. or lower by the conventional cooling panel 6. For example, the inlet valve 17.18 of the auxiliary cooling panel 11
Then, the outlet valves 22 and 23 are opened to allow the cooling pipes 215 of the auxiliary cooling panel 11 to cool. At this time, depending on the operating condition, the auxiliary cooling panel 1]-115.315.
415 cooling pipe may be used for cooling.
また、原子炉強制冷却喪失事故時には、補助冷却パネル
１１の全入口弁１７乃至２１及び全出口弁２２乃至２６
を開いて、全区分の全冷却管１０に冷却水を通水するこ
とにより充分な冷却性能を発揮させることができ、原子
炉圧力容器３及び炉心１の崩壊熱による温度上昇を低く
抑えることができる。In addition, in the event of a reactor forced cooling loss accident, all inlet valves 17 to 21 and all outlet valves 22 to 26 of the auxiliary cooling panel 11
By opening the reactor and allowing cooling water to flow through all the cooling pipes 10 in all sections, sufficient cooling performance can be achieved, and the temperature rise due to decay heat in the reactor pressure vessel 3 and the reactor core 1 can be suppressed to a low level. can.
本実施例によれば、従来と同じ温度の冷却水を用いて通
水する冷却管１０の本数をそれぞれの補助冷却パネル１
１の入口弁、出口弁で調節することにより原子炉圧力容
器３からの除熱量を調整でき、通常運転時には小さく、
原子炉強制冷却喪失事故時には大きくすることができる
。したがって原子炉通常運転時における原子炉熱効率低
下を防止し、原子炉出口温度の制約を緩和することがで
きる。また原子炉強制冷却喪失時における崩壊熱による
原子炉圧力容器３及び炉心１の温度上Ｅ４を低く抑える
ことができる。According to this embodiment, the number of cooling pipes 10 through which cooling water of the same temperature as in the past is used can be increased to each auxiliary cooling panel 1.
By adjusting the inlet valve and outlet valve 1, the amount of heat removed from the reactor pressure vessel 3 can be adjusted, and it is small during normal operation.
It can be increased in the event of a reactor forced loss of cooling accident. Therefore, it is possible to prevent a decrease in reactor thermal efficiency during normal operation of the reactor, and to ease restrictions on the reactor outlet temperature. In addition, the temperature E4 of the reactor pressure vessel 3 and the reactor core 1 due to decay heat during loss of forced reactor cooling can be suppressed to a low level.
前記実施例では補助冷却パネル１１を５本の冷却管づつ
を１区分として５区分に分割した場合について説明した
が、この区分の分割数または冷却管数は５個または５本
に限定されるものではない。In the above embodiment, a case has been described in which the auxiliary cooling panel 11 is divided into five sections, each section having five cooling pipes, but the number of divisions or the number of cooling pipes in this section is limited to five or five. isn't it.
本発明によれば、原子炉圧力容器と冷却パネルとの間に
複数本の冷却管からなる補助冷却パネルを設け、原子炉
の運転状態に応じて冷却水を通水する冷却管の本数をｍ
整するようにしたため、通常運転時は原子炉圧力容器か
らの除熱量を小さくして原子炉熱効率の低下の防止と、
原子炉出口温度の制約の緩和とを図ることができ、原子
炉強制冷却喪失時は、除熱量を大きくして、崩壊熱によ
る原子炉圧力容器及び炉心の温度上Ａ、を低く抑えるこ
とができる。According to the present invention, an auxiliary cooling panel consisting of a plurality of cooling pipes is provided between the reactor pressure vessel and the cooling panel, and the number of cooling pipes through which cooling water flows can be adjusted depending on the operating state of the reactor.
During normal operation, the amount of heat removed from the reactor pressure vessel is reduced to prevent a decline in reactor thermal efficiency.
It is possible to ease the restrictions on the reactor outlet temperature, and when forced cooling of the reactor is lost, the amount of heat removed can be increased and the temperature increase A in the reactor pressure vessel and reactor core due to decay heat can be kept low. .
第１図は本発明に係る原子炉冷却調整装置の一実施例を
示す構成図、第２図は第１図のＡ−Ａ線断面図、第３図
は従来の原子炉冷却ｍ盤装置を示す構成図、第４図は第
３図のＢ−Ｂ線断面図である。
３ 原子炉圧力容器、６ 冷却パネル、１０・冷却管、
１１・・・補助冷却パネル。Fig. 1 is a configuration diagram showing one embodiment of the reactor cooling adjustment device according to the present invention, Fig. 2 is a sectional view taken along line A-A in Fig. 1, and Fig. 3 is a diagram showing a conventional reactor cooling m-board device. The configuration diagram shown in FIG. 4 is a sectional view taken along the line BB in FIG. 3. 3 reactor pressure vessel, 6 cooling panel, 10 cooling pipe,
11... Auxiliary cooling panel.
Claims (1)
り原子炉の放熱量を冷却する原子炉冷却調整装置におい
て、前記原子炉圧力容器と前記冷却パネルとの間に複数
本の冷却管からなる補助冷却パネルを設けるとともに、
該補助冷却パネルを複数の区分に分割し、それぞれの区
分に冷却水管を接続したことを特徴とする原子炉冷却調
整装置。1. A reactor cooling adjustment device that cools the amount of heat released from the reactor using a cooling panel provided on the outer periphery of the reactor pressure vessel, which comprises a plurality of cooling pipes between the reactor pressure vessel and the cooling panel. Along with installing an auxiliary cooling panel,
A nuclear reactor cooling adjustment device characterized in that the auxiliary cooling panel is divided into a plurality of sections and a cooling water pipe is connected to each section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63325119A JP2777629B2 (en) | 1988-12-23 | 1988-12-23 | Reactor cooling adjustment device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63325119A JP2777629B2 (en) | 1988-12-23 | 1988-12-23 | Reactor cooling adjustment device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02170097A true JPH02170097A (en) | 1990-06-29 |
| JP2777629B2 JP2777629B2 (en) | 1998-07-23 |
Family
ID=18173303
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63325119A Expired - Fee Related JP2777629B2 (en) | 1988-12-23 | 1988-12-23 | Reactor cooling adjustment device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2777629B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5612982A (en) * | 1995-07-31 | 1997-03-18 | Westinghouse Electric Corporation | Nuclear power plant with containment cooling |
-
1988
- 1988-12-23 JP JP63325119A patent/JP2777629B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5612982A (en) * | 1995-07-31 | 1997-03-18 | Westinghouse Electric Corporation | Nuclear power plant with containment cooling |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2777629B2 (en) | 1998-07-23 |
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