JPS62233791A - Nuclear-reactor stoppage-time cooling device - Google Patents
Nuclear-reactor stoppage-time cooling deviceInfo
- Publication number
- JPS62233791A JPS62233791A JP61076572A JP7657286A JPS62233791A JP S62233791 A JPS62233791 A JP S62233791A JP 61076572 A JP61076572 A JP 61076572A JP 7657286 A JP7657286 A JP 7657286A JP S62233791 A JPS62233791 A JP S62233791A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- water
- line
- pressure vessel
- nuclear
- 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
- 238000001816 cooling Methods 0.000 title claims description 22
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 48
- 238000009835 boiling Methods 0.000 claims description 3
- 238000000034 method Methods 0.000 claims description 3
- 238000002347 injection Methods 0.000 claims 1
- 239000007924 injection Substances 0.000 claims 1
- 230000003134 recirculating effect Effects 0.000 claims 1
- 239000007921 spray Substances 0.000 description 23
- 241000196324 Embryophyta Species 0.000 description 11
- 238000005516 engineering process Methods 0.000 description 3
- 239000012808 vapor phase Substances 0.000 description 3
- 238000010276 construction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 238000009834 vaporization Methods 0.000 description 2
- 230000008016 vaporization Effects 0.000 description 2
- 240000000220 Panda oleosa Species 0.000 description 1
- 235000016496 Panda oleosa Nutrition 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002265 prevention 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
- Heating, Cooling, Or Curing Plastics Or The Like In General (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、沸騰水型原子力発電プラントの原子炉停止時
冷却装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a reactor shutdown cooling device for a boiling water nuclear power plant.
従来の原子炉圧力容器の冷却方法について、第２図を参
照しながら説明する。同図においてプラント停止には、
原子炉圧力容器１（以下容器と記す）から、上ｔｎ２を
取外して燃料交換ができるようになるまでは、まず容器
１全体を冷却しなければならない、しかしながら容器１
と上１ｍｔ２との接続部たる上蓋フランジを含む容器１
の上部は冷えにくい状況にあり、短時間内に冷却するた
めには特別な操作が必要である。容器１内に貯溜される
炉水の通常水位Ｌ１は、主蒸気ノズル４より若干下位に
位置していて、この水位を保ったままで炉水を冷却して
も胴体部分は除冷されるが、上蓋フランジ１７及び上鏡
２はなかなか冷えにくいから。A conventional method for cooling a nuclear reactor pressure vessel will be explained with reference to FIG. In the same figure, for plant stoppage,
Until the upper tn2 can be removed from the reactor pressure vessel 1 (hereinafter referred to as the vessel) and fuel can be replaced, the entire vessel 1 must first be cooled.
Container 1 including the upper lid flange which is the connection part between and upper 1m2
The upper part of the tank is difficult to cool down, and special operations are required to cool it down within a short period of time. The normal water level L1 of the reactor water stored in the container 1 is located slightly lower than the main steam nozzle 4, and even if the reactor water is cooled while maintaining this water level, the fuselage portion will be gradually cooled. This is because the upper lid flange 17 and upper mirror 2 do not cool easily.
容器Ｊ、の冷却はまず炉水を通常水位Ｌｌより上昇させ
、さらに上鏡２の上蓋フランジ１７を越えるまで水位を
上げてから行う、（フラッディング法）容器１の冷却は
、最初炉内蒸気を主蒸気ライン５によりブローダウンし
、容器１内の圧力が原子炉停止時冷却系で炉水を冷却で
きる圧力以下になった時点で、上蓋フランジ１７上部ま
でフラッディングを行い、再循環出口ノズル７に接続し
た再循環出口配管８より分岐した原子炉停止時冷却系の
原子炉停止時冷却用熱交換器１２（以下ＲＨＲ熱交換器
と記す）に通水し、原子炉停止時冷却系出口配管１４を
経、再循環入口配管１０、再循環入口ノズル１８により
容器１に炉水を戻し冷却を行う。ところが、容器１内の
圧力が原子炉停止時冷却系で炉水を冷却できる圧力以下
になった時点でフラッディングを開始したとしても、フ
ラッディング直前の炉水温度と容器１および上鏡２の蒸
気相部の金属温度は約１００℃位の差があり炉水は、容
器１．上鏡２および炉内構造物からの入熱で気化するた
め容器１の内圧が上昇する。The cooling of the vessel J is performed by first raising the reactor water above the normal water level Ll, and then raising the water level until it exceeds the upper cover flange 17 of the upper mirror 2 (flooding method). When the main steam line 5 blows down and the pressure inside the vessel 1 becomes lower than the pressure at which the reactor water can be cooled by the reactor shutdown cooling system, flooding is carried out to the upper part of the upper lid flange 17 and the recirculation outlet nozzle 7 is Water is passed through the reactor shutdown cooling heat exchanger 12 (hereinafter referred to as RHR heat exchanger) of the reactor shutdown cooling system branched from the connected recirculation outlet piping 8, and the reactor shutdown cooling system outlet piping 14 After that, the reactor water is returned to the vessel 1 through the recirculation inlet piping 10 and the recirculation inlet nozzle 18 for cooling. However, even if flooding is started when the pressure inside vessel 1 drops below the pressure at which the reactor shutdown cooling system can cool the reactor water, the reactor water temperature immediately before flooding and the vapor phase of vessel 1 and upper mirror 2 are There is a difference of about 100°C in the metal temperature between the reactor water and the container 1. The internal pressure of the container 1 increases due to vaporization due to heat input from the upper mirror 2 and the furnace internals.
容器１の内圧が上昇し、原子炉停止時冷却系による炉水
冷却ができなくなることを防止するために、従来プラン
トでは、フラッディング中には、ＲＨＲ熱交換器１２で
冷却した炉水の一部をヘッドスプレィライン１５．ヘッ
ドスプレィノズル３により圧力容器の蒸気相にスプレィ
注入していた。In conventional plants, during flooding, some of the reactor water cooled by the RHR heat exchanger 12 is removed in order to prevent the internal pressure of the vessel 1 from rising and the reactor water cooling system being unable to cool the reactor. Head spray line 15. A head spray nozzle 3 was used to inject a spray into the vapor phase of the pressure vessel.
そのために、Ｒ子炉停止時冷却系に５ヘツドスプレイラ
イン１５、ヘッドスプレィノズル３、上鏡２に頂部スプ
レィノズル１９を設ける必要があった。For this purpose, it was necessary to provide a five-head spray line 15, a head spray nozzle 3, and a top spray nozzle 19 on the upper mirror 2 in the R reactor shutdown cooling system.
なおこの種の技術として関連するものに、例えば特開昭
５６−１１２６８６号がある。A related technique of this type is, for example, Japanese Unexamined Patent Publication No. 112686/1986.
上記従来技術では、原子炉停止時冷却系に、ヘッドスプ
レィライン１５．ヘッドスプレィノズル３上ｆｌｔ２に
頂部スプレィノズル１９を設ける必要があった。In the above conventional technology, the head spray line 15. It was necessary to provide the top spray nozzle 19 above the head spray nozzle 3 flt2.
本発明の目的は、従来のヘッドスプレィライン１５、ヘ
ッドスプレィノズル３、および頂部スプレィノズルを排
したことにより、原子炉発電プラントの建設コストに有
利であり、しかも共用期間中検査の対象範囲を削減しプ
ラント運転コストにも有利な原子炉発電プラントを提供
することにある。The purpose of the present invention is to eliminate the conventional head spray line 15, head spray nozzle 3, and top spray nozzle, thereby reducing the construction cost of a nuclear power plant and reducing the scope of inspection during the common use period. The object of the present invention is to provide a nuclear power generation plant that is advantageous in terms of plant operating costs.
上記、従来技術では、原子炉停止時の圧力容器内圧の上
昇防止の為に、原子炉停止時冷却系に、ヘッドスプレィ
ライン１５．ヘッドスプレィノズル３を設け、上鏡２頂
部に設けた頂部スプレィノズル１９からＲＨＲ熱交換器
１２で冷却した炉水の一部を注入していた。In the above-mentioned conventional technology, in order to prevent the internal pressure of the pressure vessel from rising when the reactor is shut down, a head spray line 15. A head spray nozzle 3 was provided, and a portion of the reactor water cooled by the RHR heat exchanger 12 was injected from the top spray nozzle 19 provided at the top of the upper mirror 2.
上記圧力容器の内圧上昇防止は、従来プラントに設けら
れているベントライン２１より圧力容器の内圧を逃がす
新城圧ライン２２を分岐させ主蒸気隔離弁下流６の主蒸
気ライン５に接続することにより解決される。Prevention of the increase in the internal pressure of the pressure vessel is solved by branching the Shinshiro pressure line 22, which releases the internal pressure of the pressure vessel from the vent line 21 conventionally provided in the plant, and connecting it to the main steam line 5 downstream of the main steam isolation valve 6. be done.
プラント通常運転時には、圧力容器の内圧逃がし新ライ
ン２２の両端の設けた弁２３．および弁２４を全開とす
ることで圧力容器の内圧逃がしラインを隔離し、Ｘ子炉
停止時において炉内の水位が主蒸気ノズル４より上位に
なった時点で弁２３゜２４を全開とする。この時主蒸気
ラインに設けた弁６は全開とする。During normal plant operation, the valves 23 provided at both ends of the new internal pressure relief line 22 of the pressure vessel. The internal pressure relief line of the pressure vessel is isolated by fully opening the valve 24, and the valves 23 and 24 are fully opened when the water level in the reactor reaches a level above the main steam nozzle 4 when the X reactor is shut down. At this time, the valve 6 provided in the main steam line is fully opened.
以下１本発明の一実施例を第１図により説明する。 An embodiment of the present invention will be described below with reference to FIG.
第１図に示す沸騰水型原子力発電プラントの容器１．上
鏡２を冷却する場合、まず、主蒸気ライン５に設けた弁
６を全開とし、炉内蒸気を主蒸気ライン５によりブロー
ダウンし、容器１内の圧力が配管１１，１４、熱交換器
１２．およびポンプ１３等により構成される原子炉停止
時冷却系で炉水を冷却できる圧力まで減圧する６次に、
原子炉停止時冷却系の熱交換器１２、ポンプ１３等を作
動させ容器１内の炉水を再循環水出口ノズル７、再循環
出口配管８．より配管１１，１４、熱交換器［２，およ
びポンプ１３等で構成される原子炉停止時冷却系に吸引
し再循環水入口配管１０゜再循環水入口ノズル１８を経
て容器１内に戻し。Vessel 1 of the boiling water nuclear power plant shown in Figure 1. When cooling the upper mirror 2, first, the valve 6 provided in the main steam line 5 is fully opened, the steam in the furnace is blown down by the main steam line 5, and the pressure inside the container 1 is reduced to the pipes 11, 14 and the heat exchanger. 12. The sixth step is to reduce the pressure to a level that allows the reactor water to be cooled by the reactor shutdown cooling system consisting of pumps 13, etc.
When the reactor is shut down, the heat exchanger 12, pump 13, etc. of the cooling system are operated to recirculate the reactor water in the vessel 1 through the water outlet nozzle 7 and the recirculation outlet piping 8. Then, it is sucked into the reactor shutdown cooling system, which is composed of pipes 11, 14, heat exchanger [2, pump 13, etc.], and returned to the container 1 through the recirculation water inlet pipe 10° and the recirculation water inlet nozzle 18.
炉水の冷却を開始する。炉水の冷却を行うのに、炉水位
を主蒸気ノズル４より若干下位の通常水位Ｌ ｔに保っ
たまま行っても胴体部分は除冷されるが、上蓋フランジ
１７、および上鏡２はなかなが冷えにくい。そこで、給
水配管１６給水ノズル２５より給水を容器１内に注入し
炉水位を上鏡２頂部より若干下位に位置したレベルＬ２
まで上昇させる。その際、主蒸気ライン５に設けた弁６
を全開にしておくと炉水が主蒸気ラインを経てタービン
側に流出してしまうので、弁６はあらかじめ全開として
おく。また、炉水位の上昇にともない、容器１および上
鏡２の蒸気相部の金属からの入熱による炉水の気化等に
より容器１内の内圧が上昇する。容器１の内圧が上昇す
ると、原子炉停止時冷却系による炉水の冷却ができなく
なるので容器１の内圧を減圧する必要がある。Start cooling the reactor water. Even if the reactor water is cooled while the reactor water level is maintained at the normal water level Lt, which is slightly lower than the main steam nozzle 4, the fuselage will be slowly cooled, but the upper cover flange 17 and the upper mirror 2 will not be cooled. Kana doesn't get cold easily. Therefore, water is injected into the container 1 from the water supply nozzle 25 of the water supply piping 16 to raise the reactor water level to a level L2 located slightly below the top of the upper mirror 2.
rise to. At that time, the valve 6 installed in the main steam line 5
If valve 6 is left fully open, reactor water will flow out through the main steam line to the turbine side, so valve 6 is left fully open in advance. Further, as the reactor water level rises, the internal pressure within the container 1 increases due to vaporization of the reactor water due to heat input from the metal in the vapor phase portion of the container 1 and the upper mirror 2. If the internal pressure of the vessel 1 rises, the reactor water cannot be cooled by the reactor shutdown cooling system, so it is necessary to reduce the internal pressure of the vessel 1.
本発明では、原子炉停止時冷却の際の容器１内の減圧は
、従来プラントのベントラインより分岐した、弁２３，
２４、配管２２よりなる減圧ラインにより行う。新減圧
ラインは、主蒸気ラインによる容器１内の減圧は、従来
のベントラインに設けた弁２６．主蒸気ラインの弁６を
全開とし、新減圧ラインに設けた弁２３．２４は全開と
する。In the present invention, the pressure inside the vessel 1 during cooling during reactor shutdown is reduced by a valve 23 branched from the vent line of the conventional plant.
24, a vacuum line consisting of piping 22 is used. The new pressure reduction line allows the main steam line to reduce the pressure inside the container 1 using the valve 26. The main steam line valve 6 is fully opened, and the new pressure reducing line valves 23 and 24 are fully open.
プラント通常時においては、弁２３．２４を全閉とし、
ベントラインの弁２６および主蒸気ラインの弁６は全開
とし、ベントラインおよび主蒸気ラインは従来プラント
と全く同じ機能を維持する。During normal plant operation, valves 23 and 24 are fully closed.
The vent line valve 26 and the main steam line valve 6 are fully open, and the vent line and main steam line maintain exactly the same functions as in the conventional plant.
第１図および第２図を比軟すると分かるように、本発明
によれば、配管および弁を追設することで上鏡２のノズ
ルを従来の頂部スプレィノズル１９、ベントノズル２０
から、ベントノズル２ｏのみに削減することが可能であ
り、また、ヘッドスプレィライン１５．およびヘッドス
プレィノズル３も削減することが可能である。As can be seen by comparing FIGS. 1 and 2, according to the present invention, the nozzle of the upper mirror 2 can be replaced with the conventional top spray nozzle 19 and vent nozzle 20 by adding piping and valves.
Therefore, it is possible to reduce the number to only the vent nozzle 2o, and the head spray line 15. It is also possible to reduce the number of head spray nozzles 3.
本発明によれば、従来プラントの頂部スプレィノズル１
９．およびヘッドスプレィライン１５、ヘッドスプレィ
ノズル５を削減できるのでプラント建設コストの低減に
有利であり、しがも共用期間中検査の対象範囲も低減さ
れるのでプラント運転コストの低減にも有利である原子
炉発電プラントを提供することができる。又１本発明に
よる原子炉発電プラントでは従来プラントの機能を全く
損なうことはない。According to the invention, the top spray nozzle 1 of a conventional plant
9. The number of head spray lines 15 and head spray nozzles 5 can be reduced, which is advantageous in reducing plant construction costs.In addition, the scope of inspection during the shared use period can also be reduced, which is advantageous in reducing plant operating costs. Furnace power plants can be provided. In addition, the nuclear reactor power plant according to the present invention does not impair the functions of conventional plants at all.
第１図は本発明の一実施例の原子炉発電プラントの系統
図、第２図は従来の原子炉発電プラントの系統図である
。
■・・・原子炉圧力容器、２・・・上鏡、３・・・ヘッ
ドスプレィノズル、４・・・主蒸気ノズル、５・・・主
蒸気ライン、６・・・弁、７・・・再循環出口ノズル、
９・・・再循環ポンプ、１３・・・原子炉停止時冷却系
ポンプ、１８・・・再循環入口ノズル、１９・・・頂部
スプレィノズル、２０・・・ベントノズル、２１・・・
ベントライン、２２ＸＩ口
２１− 〜ノ計７４１FIG. 1 is a system diagram of a nuclear reactor power plant according to an embodiment of the present invention, and FIG. 2 is a system diagram of a conventional nuclear reactor power plant. ■...Reactor pressure vessel, 2...Upper mirror, 3...Head spray nozzle, 4...Main steam nozzle, 5...Main steam line, 6...Valve, 7... recirculation outlet nozzle,
9... Recirculation pump, 13... Reactor shutdown cooling system pump, 18... Recirculation inlet nozzle, 19... Top spray nozzle, 20... Vent nozzle, 21...
Vent line, 22XI port 21- ~ Total 741
Claims (1)
ライン、主蒸気ライン、ベントライン等により構成され
る沸騰水型原子力発電プラントにおいて、上部を上鏡に
より密閉された原子炉圧力容器に給水し、その水位を前
記上鏡と前記原子炉圧力容器の接続部より上昇させるこ
とによって原子炉圧力容器を冷却する方法を採用し、炉
水を所定の通常水位に保ちながら貯溜していて、前記通
常水位より下位に位置した給水ノズルより注水し、炉水
位を上昇させ前記注水による前記原子炉圧力容器内の内
圧の上昇を前記上鏡頂部に位置したベントノズルより逃
がしてやることにより防止することを特徴とした原子炉
停止時冷却装置。1. In a boiling water nuclear power plant consisting of a water supply line, recirculating water line, main steam line, vent line, etc. connected to the reactor pressure vessel, the reactor pressure vessel is sealed at the top with an upper mirror. A method is adopted for cooling the reactor pressure vessel by supplying water and raising the water level from the connection between the upper mirror and the reactor pressure vessel, and storing the reactor water while maintaining it at a predetermined normal water level, Water is injected from the water supply nozzle located below the normal water level to raise the reactor water level, and an increase in internal pressure in the reactor pressure vessel due to the water injection is prevented by escaping through the vent nozzle located at the top of the upper mirror. A nuclear reactor shutdown cooling system characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61076572A JPS62233791A (en) | 1986-04-04 | 1986-04-04 | Nuclear-reactor stoppage-time cooling device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61076572A JPS62233791A (en) | 1986-04-04 | 1986-04-04 | Nuclear-reactor stoppage-time cooling device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62233791A true JPS62233791A (en) | 1987-10-14 |
Family
ID=13608952
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61076572A Pending JPS62233791A (en) | 1986-04-04 | 1986-04-04 | Nuclear-reactor stoppage-time cooling device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62233791A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0615254A1 (en) * | 1993-03-11 | 1994-09-14 | General Electric Company | Reactor pressure vessel vented head |
| JP2010236878A (en) * | 2009-03-30 | 2010-10-21 | Toshiba Corp | Boiling water reactor |
-
1986
- 1986-04-04 JP JP61076572A patent/JPS62233791A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0615254A1 (en) * | 1993-03-11 | 1994-09-14 | General Electric Company | Reactor pressure vessel vented head |
| JP2010236878A (en) * | 2009-03-30 | 2010-10-21 | Toshiba Corp | Boiling water reactor |
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