JPH06174870A - Light-water cooled reactor - Google Patents
Light-water cooled reactorInfo
- Publication number
- JPH06174870A JPH06174870A JP4330769A JP33076992A JPH06174870A JP H06174870 A JPH06174870 A JP H06174870A JP 4330769 A JP4330769 A JP 4330769A JP 33076992 A JP33076992 A JP 33076992A JP H06174870 A JPH06174870 A JP H06174870A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- liquid supply
- pressure vessel
- cooling water
- water
- 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.)
- Withdrawn
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
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】
【目的】 軽水冷却型原子炉に係り、ほう酸水の流下性
を高めて冷却材喪失時及び一次冷却水ポンプ停止時に、
原子炉を速やかにかつ確実に停止状態に導いて安全性を
確保するとともに、原子炉格納容器の内部スペースを確
保して原子炉等のメンテナンス性を向上させる。
【構成】 原子炉格納容器の上蓋内壁に配されるポイズ
ンタンクと、原子炉圧力容器とポイズンタンクとの間に
接続状態に配される給液系配管と、給液系配管に配され
原子炉圧力容器の内部圧力の低下時に管路を開放する給
液制御手段とを具備する。
(57) [Summary] [Purpose] In relation to a light water cooling type reactor, when the flowability of boric acid water is increased and the coolant is lost and the primary cooling water pump is stopped,
To promptly and surely bring the reactor to a stopped state to ensure safety and to secure an internal space of the reactor containment vessel to improve maintainability of the reactor and the like. [Structure] A poison tank arranged on the inner wall of the upper lid of the reactor containment vessel, a liquid supply system pipe connected between the reactor pressure vessel and the poison tank, and a reactor installed on the liquid supply system pipe. And a liquid supply control means for opening the pipeline when the internal pressure of the pressure vessel drops.
Description
【0001】[0001]
【産業上の利用分野】本発明は、軽水冷却型原子炉に係
り、特に、原子炉格納容器内に原子炉圧力容器とともに
ポイズンタンクを収納する技術に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a light water cooling type nuclear reactor, and more particularly to a technique for accommodating a poison tank together with a reactor pressure vessel in a reactor containment vessel.
【0002】[0002]
【従来の技術】図2は、特開平3−252593号公報
(燃料集合体の交換装置)、特開平3−252594号
公報(燃料集合体の交換装置)、特開平3−25259
5号公報(燃料集合体の交換装置)に記載されている軽
水冷却型原子炉の例を示すものである。2. Description of the Related Art FIG. 2 is a Japanese Unexamined Patent Publication No. 3-252593 (fuel assembly exchange device), Japanese Unexamined Patent Publication No. 3-252594 (fuel assembly exchange device), and Japanese Unexamined Patent Publication No. 3-25259.
5 shows an example of a light water cooled nuclear reactor described in Japanese Patent Publication No. 5 (fuel assembly exchange device).
【0003】図2において、符号1は原子炉圧力容器、
2は炉心、3は蒸気発生器、6は一次冷却水ポンプ、1
5はライザ管、16ポイズンタンク、17は冷却水入
口、18は水圧作動弁、19はポイズン流通器、20は
炉心支持板、Pはほう酸水(炉内プール水)である。In FIG. 2, reference numeral 1 is a reactor pressure vessel,
2 is a core, 3 is a steam generator, 6 is a primary cooling water pump, 1
5 is a riser pipe, 16 poison tanks, 17 is a cooling water inlet, 18 is a hydraulically operated valve, 19 is a poison distributor, 20 is a core support plate, and P is boric acid water (pool water in the reactor).
【0004】このような構造を有する原子炉にあって
は、一次冷却水及びほう酸水が、運転時、ポンプ停止時
の相違によって、以下に記述するように異なった流通
(循環)をする。In the nuclear reactor having such a structure, the primary cooling water and the boric acid water flow differently (circulate) as described below, depending on the difference during operation and when the pump is stopped.
【0005】運転時にあっては、一次冷却水が、図2に
実線の矢印で示すように、炉心2、ライザ管15、一次
冷却水ポンプ6、蒸気発生器3、冷却水入口17を経由
して炉心2に戻る循環流となるが、ほう酸水Pは、水圧
作動弁18及びポイズン流通器19の部分で隔離され
て、挿通する現象や混合し合う現象の発生が妨げられ、
したがって、一次冷却水中のほう酸水濃度が変化するこ
となく、定常運転状態が維持される。During operation, the primary cooling water passes through the core 2, the riser pipe 15, the primary cooling water pump 6, the steam generator 3, and the cooling water inlet 17, as shown by the solid arrow in FIG. However, the boric acid water P is isolated by the hydraulically operated valve 18 and the poison distributor 19 to prevent the phenomenon of insertion and the phenomenon of mixing.
Therefore, the steady operation state is maintained without changing the boric acid water concentration in the primary cooling water.
【0006】そして、一次冷却水ポンプ6の停止時にあ
っては、蒸気発生器3への送り込みが行なわれなくなる
とともに、一次冷却水ポンプ6の吐出圧力低下検出によ
って水圧作動弁18が管路を開放した状態となり、ま
た、炉心2において引き続き加熱された一次冷却水の上
昇が生じるために、図2に破線の矢印で示すように、上
昇した一次冷却水がポイズンタンク16の内部に送り出
されるとともに、ほう酸水Pがポイズン流通器19を経
由して炉心2に流れ込み、炉心2のほう酸水濃度が高ま
ることによって核分裂反応が抑制されて自然停止に導か
れる。When the primary cooling water pump 6 is stopped, the steam generator 3 is not fed, and when the discharge pressure drop of the primary cooling water pump 6 is detected, the hydraulically operated valve 18 opens the pipeline. In addition, since the primary cooling water continuously heated in the core 2 rises, the raised primary cooling water is sent out to the inside of the poison tank 16 as shown by a dashed arrow in FIG. The boric acid water P flows into the core 2 via the poison distributor 19 and the concentration of boric acid in the core 2 increases, whereby the fission reaction is suppressed and the suspension is led to a natural stop.
【0007】このような図2例の原子炉にあっては、ポ
イズンタンク16の内外が高温状態の一次冷却水によっ
て囲まれた状態となっており、原子炉の出力が変化する
と、ほう酸水Pの液量が膨張収縮に基づいて変化し、こ
のため、ポイズン流通器19の部分において一次冷却水
とほう酸水Pとの境界が変動し易く、原子炉出力の制御
性が損われ易くなる。In the reactor shown in FIG. 2 as described above, the inside and outside of the poison tank 16 are surrounded by the primary cooling water at a high temperature, and when the output of the reactor changes, the boric acid water P The amount of liquid changes due to expansion and contraction, and therefore, the boundary between the primary cooling water and the boric acid water P easily changes at the portion of the poison distributor 19 and the controllability of the reactor output tends to be impaired.
【0008】次いで、図3例は、軽水冷却型原子炉の他
の構造例(計画例)を示すものである。該計画例にあっ
ては、原子炉格納容器21のプール水Wの中に、原子炉
圧力容器1が水漬状態に配され、ポイズンタンク22も
プール水Wの中に配される。そして、原子炉圧力容器1
とポイズンタンク22との間が、給液系配管23を構成
する均圧用配管23a及び給液用配管23bによって接
続される。この構造とすることによって、ポイズンタン
ク22が低温状態のプール水Wに収容されて、原子炉圧
力容器1からの熱的な隔離と、一次冷却水とほう酸水P
との隔離とを行なうとともに、落差及び比重差を利用し
たほう酸水Pの供給により原子炉を自然停止状態に導く
ことが可能となり、加えて、ほう酸水Pの容量を大容量
とすることができる。Next, FIG. 3 shows another structural example (plan example) of the light water cooling type reactor. In the plan example, the reactor pressure vessel 1 is placed in the pool water W of the reactor containment vessel 21 in a state of being immersed in water, and the poison tank 22 is also placed in the pool water W. And the reactor pressure vessel 1
And the poison tank 22 are connected by a pressure equalizing pipe 23a and a liquid supply pipe 23b which constitute the liquid supply system pipe 23. With this structure, the poison tank 22 is housed in the pool water W in a low temperature state, and is thermally isolated from the reactor pressure vessel 1, and the primary cooling water and the boric acid water P are contained.
It is possible to bring the reactor into a natural shutdown state by supplying the boric acid water P using the drop and the specific gravity difference, and to increase the capacity of the boric acid water P to a large capacity. .
【0009】[0009]
【発明が解決しようとする課題】しかしながら、図3例
の原子炉にあっては、原子炉圧力容器1の回りにポイズ
ンタンク22が配されて落差に制限が生じるために、ほ
う酸水Pの供給が緩やかなものとなり、一次冷却水が喪
失した場合における炉心2の冠水状態の確保や、速やか
な原子炉停止状態への誘導の点で限界がある。However, in the reactor of the example in FIG. 3, the poison tank 22 is arranged around the reactor pressure vessel 1 and the head is limited, so that the supply of the boric acid water P is performed. Is slowed down, and there is a limit in securing the submerged state of the core 2 when the primary cooling water is lost, and in promptly inducing the reactor to shut down.
【0010】本発明は、上記課題を有効に解決するもの
で、ほう酸水の流下性を高めて、冷却材喪失時及び一
次冷却水ポンプ停止時に、原子炉を速やかにかつ確実に
停止状態に導いて安全性を確保すること、原子炉格納
容器の内部スペースを確保して原子炉等のメンテナンス
性を向上させることを目的としている。The present invention effectively solves the above-mentioned problems, and enhances the flowability of boric acid water to promptly and surely bring the reactor to a stopped state when the coolant is lost and the primary cooling water pump is stopped. To secure safety and to secure the internal space of the reactor containment vessel to improve the maintainability of the reactor.
【0011】[0011]
【課題を解決するための手段】原子炉格納容器のプール
水中に原子炉圧力容器が水漬状態に配される軽水冷却型
原子炉において、原子炉格納容器の上蓋内壁に配される
ポイズンタンクと、原子炉圧力容器とポイズンタンクと
の間に接続状態に配される給液系配管と、該給液系配管
に介在状態に配され原子炉圧力容器の内部圧力の低下時
に管路を開放する給液制御手段とを具備する構成を採用
している。[Means for Solving the Problems] In a light water cooling type reactor in which a reactor pressure vessel is placed in a submerged state in pool water of a reactor containment vessel, a poison tank is provided on an inner wall of an upper lid of the reactor containment vessel. , A liquid supply system pipe arranged in a connected state between the reactor pressure vessel and a poison tank, and a pipe line opened when the internal pressure of the reactor pressure vessel decreases, which is arranged in an intervening state in the liquid supply system pipe A configuration including a liquid supply control means is adopted.
【0012】[0012]
【作用】一次冷却水ポンプの停止時や原子炉冷却水の水
位低下時に、給液制御手段が作動することにより、原子
炉圧力容器内部とポイズンタンクの内部とが連通状態と
なり、両者の大きなヘッド差に基づいてポイズンタンク
内のほう酸水が原子炉圧力容器内に流下し、ほう酸濃度
の上昇によって原子炉が自然停止状態に導かれる。上蓋
を外すことにより、ポイズンタンクの部分を原子炉格納
容器の上部開口が開放状態となり、原子炉のメンテナン
ス性が向上する。When the primary cooling water pump is stopped or the reactor cooling water level is lowered, the liquid supply control means is activated to establish communication between the inside of the reactor pressure vessel and the inside of the poison tank, and a large head of both Based on the difference, the boric acid water in the poison tank flows down into the reactor pressure vessel, and the increase of the boric acid concentration leads to the natural shutdown of the reactor. By removing the upper lid, the upper opening of the reactor containment vessel is opened in the poison tank portion, and the maintainability of the reactor is improved.
【0013】[0013]
【実施例】図1は、本発明に係る軽水冷却型原子炉の一
実施例を示すものである。図1にあって、符号18は給
液制御手段(例えば水圧作動弁)、24は上蓋、25は
ポイズンタンク、26は断熱材である。FIG. 1 shows an embodiment of a light water cooling type nuclear reactor according to the present invention. In FIG. 1, reference numeral 18 is a liquid supply control means (for example, a water pressure operated valve), 24 is an upper lid, 25 is a poison tank, and 26 is a heat insulating material.
【0014】前記上蓋24は、原子炉格納容器21の上
部開口に着脱に取り付けられる。The upper lid 24 is detachably attached to the upper opening of the reactor containment vessel 21.
【0015】前記ポイズンタンク25は、上蓋24の内
壁に一体に配され、例えば原子炉圧力容器1と同程度の
耐圧性を持つように設定されるとともに、高濃度のほう
酸水Pを貯留する。The poison tank 25 is integrally arranged on the inner wall of the upper lid 24, and is set so as to have a pressure resistance equivalent to that of the reactor pressure vessel 1, and stores a high concentration boric acid water P.
【0016】そして、原子炉圧力容器1の上部位置とポ
イズンタンク25の上部位置との間が、給液制御手段1
8を介在させた状態の均圧用配管23aによって接続さ
れ、原子炉圧力容器1の下部位置とポイズンタンク25
の下部位置との間が給液用配管23bによって接続され
ている。なお、符号23cは導圧管で、原子炉圧力容器
1と給液制御手段18との間に配されて均圧用配管23
aの一部を構成する。The liquid supply control means 1 is provided between the upper position of the reactor pressure vessel 1 and the upper position of the poison tank 25.
8 is connected by a pressure equalizing pipe 23a, and the lower position of the reactor pressure vessel 1 and the poison tank 25 are connected.
Is connected to the lower position by a liquid supply pipe 23b. Reference numeral 23c is a pressure guiding pipe, which is arranged between the reactor pressure vessel 1 and the liquid supply control means 18, and is provided with a pressure equalizing pipe 23.
It constitutes a part of a.
【0017】このような構造の軽水冷却型原子炉である
と、原子炉の運転時に一次冷却水ポンプ6が作動させら
れていると、炉心2で加熱されて高温状態となった一次
冷却水が、図1に実線の矢印で示すように、ライザ管1
5、一次冷却水ポンプ6、蒸気発生器3、冷却水入口1
7を経由して炉心2に戻る循環流となり、この際に、蒸
気発生器3の部分における熱交換によって、蒸気の発生
と一次冷却水の冷却とが行なわれる。In the light water cooling type reactor having such a structure, when the primary cooling water pump 6 is operated during the operation of the reactor, the primary cooling water heated in the core 2 to a high temperature state is generated. , The riser tube 1 as shown by the solid arrow in FIG.
5, primary cooling water pump 6, steam generator 3, cooling water inlet 1
A circulation flow returns to the core 2 via 7 and at this time, steam is generated and primary cooling water is cooled by heat exchange in the steam generator 3.
【0018】そして、一次冷却水ポンプ6の吐出圧力が
導圧管23cを経由して給液制御手段18にそれぞれ伝
送されることによって、給液制御手段18が均圧用配管
23aの管路を遮断した状態を保持し続ける。The discharge pressure of the primary cooling water pump 6 is transmitted to the liquid supply control means 18 via the pressure guiding pipe 23c, so that the liquid supply control means 18 shuts off the conduit of the pressure equalizing pipe 23a. Keep holding the state.
【0019】そして、原子炉の運転時にあっては、原子
炉圧力容器1の下方位置とポイズンタンク25の下方位
置とが接続されているために、一次冷却水の圧力上昇と
ともに、給液用配管23bの中のほう酸水Pが若干押し
上げられた位置で平衡する。したがって、ポイズンタン
ク25のほう酸水Pが原子炉圧力容器1の内部に注入さ
れることがなく、原子炉圧力容器1の内部に収納されて
いる一次冷却水及びほう酸水量に基づいて運転がなされ
る。During operation of the nuclear reactor, the lower position of the reactor pressure vessel 1 and the lower position of the poison tank 25 are connected, so that the pressure of the primary cooling water rises and the supply pipe The boric acid water P in 23b is equilibrated at a position slightly pushed up. Therefore, the boric acid water P in the poison tank 25 is not injected into the reactor pressure vessel 1, and the operation is performed based on the amounts of primary cooling water and boric acid water stored in the reactor pressure vessel 1. .
【0020】原子炉の運転中に、停電や故障等の原因に
基づいて一次冷却水ポンプ6が停止した場合には、以下
に説明するように、原子炉が受動的に自然停止状態に導
かれる。When the primary cooling water pump 6 is stopped due to a cause such as a power failure or a failure during the operation of the nuclear reactor, the nuclear reactor is passively led to a naturally stopped state as described below. .
【0021】一次冷却水ポンプ6が停止すると、ポンプ
吐出圧力の低下または圧力消滅が、導圧管23cを経由
して給液制御手段18に伝達され、給液制御手段18の
作動によって均圧用配管23aによる管路が開放状態に
導かれる。原子炉圧力容器1の下部位置とポイズンタン
ク25の下部位置との連通に加えて、原子炉圧力容器1
の上部位置とポイズンタンク25の上部位置とが接続さ
れることによって、原子炉圧力容器1の気相部分の蒸気
がポイズンタンク25に送り込まれて、ポイズンタンク
25に気相部分が形成されることによる均圧化が図ら
れ、ポイズンタンク25と原子炉圧力容器1との水頭差
に基づいて、ほう酸水Pが図1の破線の矢印で示すよう
に、原子炉圧力容器1の内部に注入される。ほう酸水P
が炉心2に送り込まれると、炉心2の冷却と核反応抑制
とによって原子炉が自然停止状態に導かれる。When the primary cooling water pump 6 is stopped, the decrease or disappearance of the pump discharge pressure is transmitted to the liquid supply control means 18 through the pressure guiding pipe 23c, and the liquid supply control means 18 operates to equalize the pressure distribution pipe 23a. The conduit is guided to the open state. In addition to communication between the lower position of the reactor pressure vessel 1 and the lower position of the poison tank 25, the reactor pressure vessel 1
Is connected to the upper position of the poison tank 25, the vapor of the vapor phase portion of the reactor pressure vessel 1 is sent to the poison tank 25 and the vapor phase portion is formed in the poison tank 25. Based on the head difference between the poison tank 25 and the reactor pressure vessel 1, boric acid water P is injected into the reactor pressure vessel 1 as indicated by the broken arrow in FIG. It Boric acid water P
Is sent to the core 2, the reactor is brought into a spontaneous shutdown state by cooling the core 2 and suppressing the nuclear reaction.
【0022】原子炉運転中に、一次冷却系のなんらかの
故障に起因して、炉水が低下する現象が発生した場合
(冷却材喪失時)には、一次冷却水の水位レベルが一次
冷却水ポンプ6のポンプ吸引口の下方位置まで低下する
と、一次冷却水ポンプ6が気体分を吸い込むことに基づ
いて吐出圧力が低下し、一次冷却水ポンプ6が停止した
場合と同様に、給液制御手段18が均圧用配管23aの
管路を開放し、ポイズンタンク25のほう酸水Pが炉心
2に送り込まれ、炉心2の冠水状態の保持と原子炉停止
とが行なわれる。During a reactor operation, when a phenomenon occurs in which the reactor water drops due to some failure of the primary cooling system (when the coolant is lost), the level of the primary cooling water is changed to the primary cooling water pump. When it is lowered to a position below the pump suction port of 6, the discharge pressure is lowered due to the primary cooling water pump 6 sucking in the gas component, and the liquid supply control means 18 is provided as in the case where the primary cooling water pump 6 is stopped. Opens the line of the pressure equalizing pipe 23a, the boric acid water P in the poison tank 25 is sent to the reactor core 2, and the flooded state of the reactor core 2 is maintained and the reactor is shut down.
【0023】一方、ポイズンタンク25の部分は、上蓋
24の部分と一緒に原子炉格納容器21から外し得るも
のとなり、また、図3例と比較して、ポイズンタンク2
5やその支持構造物が、原子炉格納容器21の内部から
撤去されることによって、原子炉圧力容器1の周囲から
原子炉格納容器21の上部開口までの間が開放される。
したがって、原子炉格納容器21の内部における各種メ
ンテナンス性が向上するものとなる。On the other hand, the portion of the poison tank 25 can be removed from the reactor containment vessel 21 together with the portion of the upper lid 24, and in comparison with the example of FIG.
By removing 5 and its supporting structure from the inside of the reactor containment vessel 21, a space between the periphery of the reactor pressure vessel 1 and the upper opening of the reactor containment vessel 21 is opened.
Therefore, various maintainability inside the reactor containment vessel 21 is improved.
【0024】[0024]
【発明の効果】本発明に係る軽水冷却型原子炉によれ
ば、以下の効果を奏する。 (1) 原子炉格納容器の上蓋内壁に配されるポイズン
タンクと、原子炉圧力容器とポイズンタンクとの間に接
続状態に配される給液系配管と、給液系配管に配され原
子炉圧力容器の内部圧力の低下時に管路を開放する給液
制御手段とを具備する構成の採用によって、従来技術と
比較してほう酸水の供給時の流下性を高めて、冷却材喪
失時及び一次冷却水ポンプ停止時に、原子炉を速やかに
かつ確実に停止状態に導いて安全性を確保することがで
きる。 (2) 原子炉圧力容器の回りからポイズンタンクをな
くすことによって、原子炉圧力容器を水浸状態とする場
合にあっても、原子炉格納容器の内部スペースを確保し
て原子炉等のメンテナンス性を向上させることができ
る。 (3) 原子炉圧力容器の上蓋にポイズンタンクを一体
化状態に配することにより、ほう酸水給液のための水頭
差の設定の自由度を向上させることができる。The light water cooled nuclear reactor according to the present invention has the following effects. (1) A poison tank arranged on the inner wall of the upper lid of the reactor containment vessel, a liquid supply system pipe connected between the reactor pressure vessel and the poison tank, and a reactor arranged on the liquid supply system pipe. By adopting a configuration provided with a liquid supply control means for opening the pipeline when the internal pressure of the pressure vessel decreases, the flowability at the time of supplying boric acid water is enhanced as compared with the prior art, and at the time of loss of coolant and primary When the cooling water pump is stopped, the reactor can be promptly and surely brought to a stopped state to ensure safety. (2) By removing the poison tank from around the reactor pressure vessel, the internal space of the reactor containment vessel is secured even when the reactor pressure vessel is immersed in water to maintain the reactor. Can be improved. (3) By arranging the poison tank integrally with the upper lid of the reactor pressure vessel, it is possible to improve the degree of freedom in setting the head difference for supplying boric acid water.
【図1】本発明に係る軽水冷却型原子炉の一実施例を示
す正断面図である。FIG. 1 is a front sectional view showing an embodiment of a light water cooling-type nuclear reactor according to the present invention.
【図2】軽水冷却型原子炉の従来例を示す正断面図であ
る。FIG. 2 is a front sectional view showing a conventional example of a light water cooling type nuclear reactor.
【図3】軽水冷却型原子炉の計画例を示す正断面図であ
る。FIG. 3 is a front sectional view showing an example of a plan of a light water cooling type reactor.
1 原子炉圧力容器 2 炉心 3 蒸気発生器 6 一次冷却水ポンプ 15 ライザ管 17 冷却水入口 18 給液制御手段(水圧作動弁) 21 原子炉格納容器 23 給液系配管 23a 均圧用配管 23b 給液用配管 23c 導圧管 24 上蓋 25 ポイズンタンク 26 断熱材 P ほう酸水(炉内プール水) W プール水 1 Reactor Pressure Vessel 2 Core 3 Steam Generator 6 Primary Cooling Water Pump 15 Riser Pipe 17 Cooling Water Inlet 18 Liquid Supply Control Means (Water Pressure Operated Valve) 21 Reactor Containment Vessel 23 Liquid Supply System Pipe 23a Pressure Equalizing Pipe 23b Liquid Supply Piping 23c Pressure guiding pipe 24 Upper lid 25 Poison tank 26 Insulation material P Boric acid water (in-reactor pool water) W Pool water
Claims (1)
力容器が水漬状態に配される軽水冷却型原子炉であっ
て、原子炉格納容器の上蓋内壁に配されるポイズンタン
クと、原子炉圧力容器とポイズンタンクとの間に接続状
態に配される給液系配管と、該給液系配管に介在状態に
配され原子炉圧力容器の内部圧力の低下時に管路を開放
する給液制御手段とを具備することを特徴とする軽水冷
却型原子炉。1. A light water cooling type nuclear reactor in which a reactor pressure vessel is placed in a pooled water of a reactor containment vessel in a submerged state, and a poison tank arranged on an inner wall of an upper lid of the reactor containment vessel, A liquid supply system pipe arranged in a connected state between the reactor pressure vessel and a poison tank, and a liquid supply system which is arranged in an intervening state in the liquid supply system pipe and opens the pipeline when the internal pressure of the reactor pressure vessel decreases. A light water cooled nuclear reactor comprising: a control means.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4330769A JPH06174870A (en) | 1992-12-10 | 1992-12-10 | Light-water cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4330769A JPH06174870A (en) | 1992-12-10 | 1992-12-10 | Light-water cooled reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH06174870A true JPH06174870A (en) | 1994-06-24 |
Family
ID=18236339
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4330769A Withdrawn JPH06174870A (en) | 1992-12-10 | 1992-12-10 | Light-water cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH06174870A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2497756A (en) * | 2011-12-19 | 2013-06-26 | Charles Donald Ingham | A process for the rapid shut-down of nuclear fission reactions |
| CN107785084A (en) * | 2017-07-31 | 2018-03-09 | 清华大学天津高端装备研究院 | A kind of integrated cold containers type reactor of self-pressurization type |
| WO2019164584A3 (en) * | 2017-12-29 | 2019-12-12 | Nuscale Power, Llc | Controlling a nuclear reaction |
| CN115083646A (en) * | 2022-06-23 | 2022-09-20 | 华能核能技术研究院有限公司 | Method for quickly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor |
-
1992
- 1992-12-10 JP JP4330769A patent/JPH06174870A/en not_active Withdrawn
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2497756A (en) * | 2011-12-19 | 2013-06-26 | Charles Donald Ingham | A process for the rapid shut-down of nuclear fission reactions |
| CN107785084A (en) * | 2017-07-31 | 2018-03-09 | 清华大学天津高端装备研究院 | A kind of integrated cold containers type reactor of self-pressurization type |
| CN107785084B (en) * | 2017-07-31 | 2023-10-27 | 清华大学天津高端装备研究院 | Self-pressurization type integrated cold vessel type reactor |
| WO2019164584A3 (en) * | 2017-12-29 | 2019-12-12 | Nuscale Power, Llc | Controlling a nuclear reaction |
| US11309094B2 (en) | 2017-12-29 | 2022-04-19 | Nuscale Power, Llc | Controlling a power output of a nuclear reaction without control rods |
| US11380448B2 (en) | 2017-12-29 | 2022-07-05 | Nuscale Power, Llc | Controlling a power output of a nuclear reaction without control rods |
| US11527334B2 (en) | 2017-12-29 | 2022-12-13 | Nuscale Power, Llc | Boron injection system for controlling a nuclear reaction by delivering boron into a containment vessel |
| US11996208B2 (en) | 2017-12-29 | 2024-05-28 | Nuscale Power, Llc | Controlling a power output of a nuclear reactor without using control rods |
| US12100523B2 (en) | 2017-12-29 | 2024-09-24 | Nuscale Power, Llc | Controlling a power output of a nuclear reaction using chemical injection |
| US12537110B2 (en) | 2017-12-29 | 2026-01-27 | Nuscale Power, Llc | Passive chemical injection system for controlling a nuclear reaction by delivering a neutron-absorbing chemical into a containment vessel |
| CN115083646A (en) * | 2022-06-23 | 2022-09-20 | 华能核能技术研究院有限公司 | Method for quickly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor |
| CN115083646B (en) * | 2022-06-23 | 2023-06-27 | 华能核能技术研究院有限公司 | Method for rapidly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20000307 |