JPH077091B2 - Boiling water reactor - Google Patents
Boiling water reactorInfo
- Publication number
- JPH077091B2 JPH077091B2 JP61171610A JP17161086A JPH077091B2 JP H077091 B2 JPH077091 B2 JP H077091B2 JP 61171610 A JP61171610 A JP 61171610A JP 17161086 A JP17161086 A JP 17161086A JP H077091 B2 JPH077091 B2 JP H077091B2
- Authority
- JP
- Japan
- Prior art keywords
- steam
- water
- separator
- stand pipe
- nuclear reactor
- 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
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Classifications
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- 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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- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Separating Particles In Gases By Inertia (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、沸騰水型原子炉に関し、特に簡単な構造でか
つ十分な気水分離性能をもつものに係る。Description: TECHNICAL FIELD The present invention relates to a boiling water nuclear reactor, and particularly to a boiling water nuclear reactor having a simple structure and sufficient steam separation performance.
従来の沸騰水型原子炉の原子炉炉心上部の気水分離装置
は気水分離器及びその上方の蒸気乾燥器からなる。The steam-water separator at the upper part of the reactor core of a conventional boiling water reactor comprises a steam-water separator and a steam dryer above it.
気水分離器はたて型軸流遠心式でシユラウドヘツド上方
に複数個(200ケ程度)の気水分離ユニツトを平行に並
べたものである。気水分離器の構造を第2図に示す。炉
心を出た気水混合液体は炉心上部のプレナムからスタン
ドパイプ3を経て気水分離器の下端に入り、ここで入口
ベーン12により回転運動が与えられ、チユーブ13内を自
由うず巻き運動で上向きに移動して行く間に、それに伴
なう遠心力効果によつて水と蒸気が分離される。チユー
ブ頂部14で水分は集合して降下する。一方、蒸気分はそ
のまま軸方向に上向きに進んで、蒸気乾燥器へ入る。The air / water separator is a vertical axial flow centrifugal type, and a plurality (about 200) of water / water separation units are arranged in parallel above the shell head. The structure of the steam separator is shown in FIG. The steam-water mixed liquid leaving the core enters the lower end of the steam-water separator from the plenum at the upper part of the core through the stand pipe 3 and is given a rotational motion by the inlet vane 12 where it is swirled upward in the tube 13 by free swirling motion. As it travels, water and steam are separated due to the centrifugal effects that accompany it. At the top of the tube 14, water gathers and falls. On the other hand, the steam component goes axially upward and enters the steam dryer.
蒸気乾燥器は平行波板をまとめたものである。その構造
を第3図に示す。蒸気は波板の間を通る間に進行方向が
何回も変り、方向変換ごとに蒸気中の水分が波板状の表
面に当り湿気を除かれた後、主蒸気管へ導びかれる。分
離されたドレンは蒸気乾燥器ドレン管16より外部へ導び
かれる。The steam dryer is a collection of parallel corrugated plates. The structure is shown in FIG. The steam changes its traveling direction many times while passing between corrugated plates, and the water in the steam is guided to the main steam pipe after the moisture in the steam hits the corrugated plate-shaped surface to remove the moisture. The separated drain is guided to the outside through the steam dryer drain pipe 16.
大型原子炉では上記2種類の湿分分離装置で出口混分0.
1wt%以下という十分な性能をあげているが、一方これ
らの装置による蒸気の圧力損失が無視できないこと、燃
料交換の際にはこれらの装置を炉外に取り出す必要があ
るが重量が重く移送に手間がかかること、又、構造が複
雑であるため使用期間中検査に労力を必要とし、その間
の検査員がある程度被ばくを受けること等の欠点があ
る。In large reactors, the two types of moisture separators described above can be used to reduce the outlet mixture.
Although it has a sufficient performance of 1 wt% or less, the pressure loss of steam due to these devices cannot be ignored, and it is necessary to take these devices out of the furnace at the time of refueling, but the weight is heavy and they are not transferred. There are drawbacks in that it takes time and labor is required for the inspection due to its complicated structure, and the inspector during that period is exposed to some extent.
なお、その他の気液分離装置としては、抽気の湿分分離
器があるが、これは波板型もしくは細孔型湿分分離器で
ある。As another gas-liquid separator, there is a bleeder moisture separator, which is a corrugated plate type or a micropore type moisture separator.
上記従来技術は、出力及び出力密度の高い大型原子炉用
として採用されているものである。大型原子炉では出力
密度が高いため気水分離器へ進入してくる蒸気に随伴さ
れる水分の割合が多く従来例のような高性の気水分離器
及び蒸気乾燥器で十分湿分を除去する必要があつた。し
かし、中小型炉では出力密度が低いため、従来例のよう
な大がかりな気水分離装置は必要とせず、軽量かつメン
テナンス性のよい気水分離装置が望まれる。The above-mentioned conventional technique is adopted for a large-scale nuclear reactor having high power and high power density. Large reactors have a high power density, so the steam that enters the steam-water separator has a large proportion of water, and the high-performance steam-water separator and steam dryer as in the conventional example remove sufficient moisture. I needed to do it. However, since the power density is low in small and medium-sized furnaces, a large-scale air / water separator unlike the conventional example is not required, and a light-water / water separator having good maintainability is desired.
本発明の目的は、中小型原子炉用の気水分離装置とし
て、軽量でメンテナンス性がよく、かつ圧力損失の少な
い気水分離装置を提供することにある。An object of the present invention is to provide a steam / water separator for a small-to-medium-sized nuclear reactor, which is lightweight, has good maintainability, and has a small pressure loss.
上記目的を達成するための手段を以下に示す。 The means for achieving the above object will be described below.
出力密度の高い大型原子炉では炉心の単位体積当りのボ
イド発生量が多いため、それに伴なつて蒸気の上昇速度
は速くなる。従つてそれに随伴されて水分も上方までお
し上げられ、いわいるスラグ流(蒸気中に大きな水魂を
含んだ状態)の領域が炉心上部まで持続する。すなわ
ち、第4図に示すように、炉心部の湿分量はエレベーシ
ヨンと伴にゆるやかに低下し、炉心上部及びスタンドパ
イプ部分においても相当量の湿分が存在する。従つて大
型炉では遠心式気水分離器により、大量の湿分をとり除
く必要があつた。In large reactors with high power density, the amount of voids generated per unit volume of the core is large, and the rate of vapor rise increases accordingly. Therefore, the water accompanying it is also lifted up, and the so-called slag flow region (a state in which a large water soul is contained in the steam) continues up to the upper core. That is, as shown in FIG. 4, the moisture content in the core portion gradually decreases with elevation, and a considerable amount of moisture is present in the core upper portion and the stand pipe portion. Therefore, in a large reactor, it was necessary to remove a large amount of moisture with a centrifugal steam separator.
一方、出力密度の低い中小型原子炉では、炉心部の体積
当り蒸気発生量が少ないため、水分の随伴量は少なく、
比較的ゆるやかな沸騰状態となる。すなわち、第4図に
示すように、炉心部の湿分量は、炉心上部で急激に低下
し、スタンドパイプ部での湿分は低い。従つて従来のよ
うな高性能の気水分離器は必要としない。On the other hand, in small and medium-sized nuclear reactors with low power density, the amount of steam generated per volume in the core is small, so the amount of water entrained is small,
It will be in a relatively gentle boiling state. That is, as shown in FIG. 4, the moisture content in the core portion drops sharply in the upper portion of the core, and the moisture content in the stand pipe portion is low. Therefore, the conventional high-performance steam separator is not required.
この観点もふまえて、気液分離手段として、重力落下式
気水分離領域を設けることをねらい、具体的には、原子
炉内のスタンドパイプと主蒸気配管入口との間の蒸気流
路途中に空洞領域を設け、前記空洞領域の高さを前記空
洞領域へ下方から上方へ蒸気を吐出する機器からの直径
3cm以上の水滴の最大到達高さよりも高く、前記空洞領
域の蒸気流路断面積を前記スタンドパイプの流路断面積
よりも広くしたことを特徴とする沸騰水型原子炉とした
ものである。Based on this point of view, as a gas-liquid separation means, aiming to provide a gravity drop type water-water separation area, specifically, in the middle of the steam flow path between the stand pipe in the reactor and the main steam pipe inlet. The diameter from the equipment that provides the cavity area and discharges the height of the cavity area from below to above the cavity area.
The boiling water reactor is characterized in that it is higher than the maximum arrival height of water droplets of 3 cm or more and the steam flow passage cross-sectional area of the cavity region is wider than the flow passage cross-sectional area of the stand pipe.
空洞領域に下方から気水混合流体を注入し、その空洞領
域で水滴を重力落下により除去し水分のすくない蒸気を
ひき出す作用を得る。A mixture of air and water is injected into the hollow region from below, and water drops are removed by gravity falling in the hollow region to obtain the action of drawing out steam with less water content.
以下、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.
炉心部1の上方にあるシユラウドヘツド2から複数個
(200本程度)のスタンドパイプ3を設け、炉心で発生
した蒸気及び随伴する水分をスタンドパイプ3を通つて
気水分離装置4に導く。なお、スタンドパイプ3の直径
は、水の上昇速度を抑えるため、大型炉のものより太い
直径11cm程度とする。又、スタンドパイプ3の長さは、
水面からスタンドパイプ上端が露出するよう、シユラウ
ドヘツド2最頂部より50mm程度の長さとし、上部プレナ
ム水5の水位はシユラウドヘツド最頂部2より30cm程度
とする。気水分離器4は直径3cm程度以上の水滴を重力
落下により除去できるように、高さを約5m、直径は圧力
容器内径と等しい約6mとする。重力により分離された水
分は上部プレナム水5上に落下し、炉心下部に再循環す
る。A plurality of (about 200) stand pipes 3 are provided from the shell head 2 above the core portion 1, and steam generated in the core and accompanying moisture are guided to the steam separator 4 through the stand pipe 3. The diameter of the stand pipe 3 is about 11 cm, which is thicker than that of a large-scale furnace in order to suppress the rising speed of water. Also, the length of the stand pipe 3 is
The length of the upper plenum water 5 shall be about 30 cm from the top of the shroud head so that the upper end of the stand pipe is exposed from the water surface. The water / water separator 4 has a height of about 5 m and a diameter of about 6 m, which is equal to the inner diameter of the pressure vessel, so that water drops having a diameter of about 3 cm or more can be removed by gravity fall. The water separated by gravity falls on the upper plenum water 5 and is recirculated to the lower part of the core.
水分が分離され蒸気は上方へ進み、気水分離装置上方に
ある蒸気乾燥器6に入り、ミスト状の水滴をさらに除去
した後、主蒸気配管7を通つてタービンに運ばれる。The water is separated and the steam moves upward, enters the steam dryer 6 above the steam separator, further removes mist-like water droplets, and then is conveyed to the turbine through the main steam pipe 7.
本実施例によれば、従来例と比べて、遠心式気水分離器
がなくなり、大きな空洞部ができたこと、スタンドパイ
プの長さが50cm程度まで短縮されたことにより、従来例
では約0.8kg/cm2あつたこの部分の圧損が、事実上0と
なる。又、蒸気乾燥器部分の圧損は気水分離器部分と比
べて無視できる程度である。この圧損の減少による熱効
率の向上は熱出力換算した場合0.15%に相当する。According to this embodiment, compared with the conventional example, the centrifugal steam separator was eliminated, a large cavity was created, and the length of the stand pipe was shortened to about 50 cm. The pressure loss in the kg / cm 2 atmosphere is virtually zero. Further, the pressure loss of the steam dryer portion is negligible as compared with the steam separator portion. The improvement in thermal efficiency due to the decrease in pressure loss corresponds to 0.15% in terms of heat output.
又、燃料交換を行う際に移送することが必要な気水分離
器(シユラウドヘツド)の重量を大巾に低減することに
より、原子炉開放、閉鎖作業が迅速に行えるようにな
る。Further, by significantly reducing the weight of the steam separator (shroud head) that needs to be transferred when refueling, the reactor opening and closing operations can be performed quickly.
さらに、複雑な形状の遠心式気水分離器がなくなること
により、溶接部等の使用期間中の検査が不要となり、作
業員の被曝低減効果にも寄与する。Further, since the centrifugal type water-water separator having a complicated shape is eliminated, it is not necessary to inspect the welded portion or the like during its use period, which contributes to the effect of reducing the radiation exposure of the worker.
スタンドパイプから蒸気に随伴されて放出される水滴
は、その水滴の大きさにより2種類の機構により重力落
下し除去される。Water droplets discharged from the stand pipe in association with steam are gravity-dropped and removed by two kinds of mechanisms depending on the size of the water droplets.
(1)大きな水滴はスタンドパイプからある初速度v0で
吸き出されると、その初速度に従つた放出線軌道を描
き、重力により落下する。従つて気水分離器の高さは、
これらの水滴の最大到達高さより高くする必要がある。(1) When a large water drop is sucked out of the stand pipe at a certain initial velocity v 0, it draws an emission line trajectory according to the initial velocity and falls due to gravity. Therefore, the height of the steam separator is
It should be higher than the maximum reaching height of these water drops.
(2)小さな水滴については、落下速度が空気抵抗とつ
り合う時点で最終落下速度が規定される。従つて、空間
内の蒸気上昇速度が最大落下速度より大きな場合は、水
滴は落下できず蒸気と伴に上方に押し上げられてしま
う。従つて十分小さな水滴が落下し得るように蒸気流速
を低下させるため十分な空間の断面積が必要となる。(2) For small water drops, the final drop velocity is defined when the drop velocity balances the air resistance. Therefore, when the vapor rising speed in the space is higher than the maximum falling speed, the water droplets cannot fall and are pushed upward together with the steam. Therefore, a sufficient space cross-sectional area is required to reduce the steam flow velocity so that sufficiently small water droplets can fall.
以下、上記の機構より必要となる気水分離装置の仕様を
定量的に評価する。Hereinafter, the specifications of the steam separation device required by the above mechanism will be quantitatively evaluated.
(1)空間高さ 初速度v0の粒子の最大到達高さは以下の式で表わせる。(1) Spatial height The maximum arrival height of a particle with an initial velocity v 0 can be expressed by the following formula.
x=v0 2/2g ……(1) 今、中小型炉の水滴の初速度は大型炉の半分である6m/s
程度であるので、xは18mと非常に大きくなる。これを
低減するためには、スタンドパイプの直径を大きくし
て、速度を下げるかスタンドパイプの方向をななめにし
て、放出された水滴が横壁に当るようにすればよい。な
お、空間高さを5m程度とするためには、スタンドパイプ
直径を従来の約8cmから11cm程度に増加されせばよい。x = v 0 2 / 2g (1) Now, the initial velocity of water droplets in small and medium-sized reactors is 6m / s, which is half that in large reactors.
Since it is a degree, x becomes very large at 18 m. In order to reduce this, the diameter of the stand pipe may be increased, the speed may be reduced or the direction of the stand pipe may be licked so that the discharged water droplets hit the lateral wall. In order to set the space height to about 5 m, the diameter of the stand pipe may be increased from about 8 cm to about 11 cm.
(2)空間断面積 粒子の落下抵抗による最終速度は、 c:抵抗係数(球形の場合1) ρ:雰囲気密度(36kg/m3) f:断面積 の式で表せる。(2) Spatial cross-section area The final velocity due to particle drop resistance is c: Resistance coefficient (1 for spherical shape) ρ: Atmosphere density (36kg / m 3 ) f: Cross sectional area
中小型炉のプレナム部の蒸気速度は大型炉の半分である
1m/s程度であるから、(2)式よりこの空間で直径3cm
以上の水滴は落下除去することが可能となる。Vapor velocity in the plenum of small and medium-sized reactors is half that of large reactors
Since it is about 1 m / s, the diameter is 3 cm in this space from equation (2).
The above water drops can be dropped and removed.
本発明の第2実施例は次の如くである。The second embodiment of the present invention is as follows.
重力落下による湿分分離効果を蒸気乾燥器に適用した図
を第5図に示す。気水分離器8の上方に折流手段として
の円筒9を設け、気水分離器8から放出された水分を含
む蒸気を円筒内を上昇させる。ここで大きな水滴は重力
落下により除去される。蒸気は一旦トツプヘツド10近く
まで達した後、円筒9の外側に下降して主蒸気配管7よ
りタービンへ進む。円筒9内で重力落下からのがれた水
滴はトツプヘツド10に慣性で衝突し除去される。除去さ
れた水滴は圧力容器壁及び円筒9の壁をつたつてドレン
され、炉心下方に再循環する。Fig. 5 shows a diagram in which the effect of separating moisture by gravity is applied to a steam dryer. A cylinder 9 serving as a flow diverter is provided above the steam separator 8 so that the steam containing water released from the steam separator 8 rises in the cylinder. Here, large water drops are removed by gravity fall. The steam once reaches near the top head 10, then descends to the outside of the cylinder 9 and advances from the main steam pipe 7 to the turbine. Water drops that have fallen off due to gravity falling in the cylinder 9 collide with the top head 10 by inertia and are removed. The removed water drops are drained by connecting the wall of the pressure vessel and the wall of the cylinder 9 and recirculated to the lower side of the core.
又、第6図に示す本発明の第3実施例は折流手段として
のエルボ配管又はL字型トンネル11を主蒸気管入口に設
けることによつても、同様の効果が得られる。この場
合、円筒9を設けた場合より、蒸気上昇のための断面積
を大きくできるため、蒸気上昇速度はより遅くなり、重
力落下による気水分離効果が大きくなる。The third embodiment of the present invention shown in FIG. 6 can also obtain the same effect by providing an elbow pipe or an L-shaped tunnel 11 as a flow diverting means at the main steam pipe inlet. In this case, since the cross-sectional area for ascending the steam can be made larger than the case where the cylinder 9 is provided, the ascending speed of the steam becomes slower, and the effect of separating water and water by gravity falling becomes greater.
本発明の第4,第5実施例は次の如くである。The fourth and fifth embodiments of the present invention are as follows.
本発明を中小型の沸騰水型自然循環炉に適用した図を第
7図及び第8図に示す。FIGS. 7 and 8 are diagrams in which the present invention is applied to a small-to-medium-sized boiling water type natural circulation furnace.
第4実施例である第7図は重力落下による湿分分離効果
を気水分離器に適用した例であり、第5実施例である第
8図は同効果を蒸気乾燥器に適用した例である。FIG. 7, which is the fourth embodiment, is an example in which the moisture separation effect by gravity fall is applied to a steam separator, and FIG. 8, which is the fifth embodiment, is an example in which the same effect is applied to a steam dryer. is there.
沸騰水型自然循環炉の場合、炉心部1の出力密度が低
く、発生した蒸気の流速が遅いため、水滴の重力落下に
よる湿分分離効果は高い。In the case of a boiling water type natural circulation reactor, since the power density of the core part 1 is low and the generated steam has a low flow velocity, the effect of separating moisture by gravity drop of water droplets is high.
本発明によれば、遠心式気水分離器もしくは、平行波板
型蒸気乾燥器が不要となるため、圧損の低減による熱効
率の向上、炉内構造物の簡素化によるコスト低減および
原子炉開放閉鎖作業の簡単化そして炉内構造物の溶接線
が減少することによる検査の簡単化及びそれに伴なう作
業員被ばく線量の低減の効果がある。According to the present invention, since the centrifugal steam-water separator or the parallel wave plate type steam dryer is not required, the thermal efficiency is improved by reducing the pressure loss, the cost is reduced by simplifying the internal structure of the reactor, and the reactor is closed and closed. This has the effect of simplifying the work and reducing inspection lines due to the reduction of the welding lines of the in-core structure and the accompanying reduction in the worker's exposure dose.
第1図は本発明の第1実施例による原子炉断面図、第2
図は従来の原子炉内における遠心式気水分離器の縦断
面、第3図は従来の原子炉内における波板型蒸気乾燥器
の要部斜視図、第4図は高出力密度炉心と低出力密度炉
心のエレベーシヨンごとの水分含有率を示すグラフ図、
第5図は本発明の第2実施例による原子炉断面図、第6
図は本発明の第3実施例による原子炉断面図、第7図は
本発明の第4実施例であつて、中小型の沸騰水型原子炉
に適用した場合の原子炉断面図、第8図は同じく第4実
施例による原子炉断面図である。 1……炉心部、2……シユラウドヘツド、3……スタン
ドパイプ、4……気水分離装置、5……上部プレナム
水、6……蒸気乾燥器、7……主蒸気配管、8……気水
分離器、9……円筒、10……トツプヘツド、11……エル
ボ配管、12……入口ベーン、13……チユーブ、14……チ
ユーブ頂部、15……波板、16……ドレン管。FIG. 1 is a sectional view of a nuclear reactor according to a first embodiment of the present invention, and FIG.
Figure is a vertical cross section of a centrifugal steam-water separator in a conventional nuclear reactor, Figure 3 is a perspective view of the main parts of a corrugated plate steam dryer in a conventional nuclear reactor, and Figure 4 is a high power density core and low A graph showing the water content for each elevation of the power density core,
FIG. 5 is a sectional view of a reactor according to a second embodiment of the present invention,
FIG. 7 is a cross-sectional view of a reactor according to a third embodiment of the present invention, and FIG. 7 is a fourth embodiment of the present invention, which is a cross-sectional view of a reactor when applied to a small-to-medium-sized boiling water reactor, The figure is also a sectional view of a nuclear reactor according to the fourth embodiment. 1 ... Core part, 2 ... Shroud head, 3 ... Stand pipe, 4 ... Steam-water separator, 5 ... Upper plenum water, 6 ... Steam dryer, 7 ... Main steam pipe, 8 ... Steam Water separator, 9 ... Cylinder, 10 ... Top head, 11 ... Elbow piping, 12 ... Inlet vane, 13 ... Chew, 14 ... Chube top, 15 ... Corrugated plate, 16 ... Drain pipe.
Claims (3)
口との間の蒸気流路途中に空洞領域を設け、前記空洞領
域の高さを前記空洞領域へ下方から上方へ蒸気を吐出す
る機器からの直径3cm以上の水滴の最大到達高さよりも
高く、前記空洞領域の蒸気流路断面積を前記スタンドパ
イプの流路断面積よりも広くしたことを特徴とする沸騰
水型原子炉。1. A device for providing a hollow region in the middle of a steam flow path between a stand pipe in a nuclear reactor and an inlet of a main steam pipe, and discharging steam from the lower part to the upper part of the height of the hollow region to the hollow region. The boiling water reactor is characterized in that it is higher than the maximum arrival height of water droplets having a diameter of 3 cm or more from, and the steam channel cross-sectional area of the cavity region is wider than the channel cross-sectional area of the stand pipe.
と蒸気乾燥器との間に備え、前記空洞領域へ下方から上
方へ蒸気を吐出する機器は前記スタンドパイプであるこ
とを特徴とする特許請求の範囲の第1項に記載の沸騰水
型原子炉。2. The hollow region is provided between a stand pipe and a steam dryer in a nuclear reactor, and a device for discharging steam from the lower part to the upper part of the hollow region is the stand pipe. The boiling water nuclear reactor according to claim 1.
蒸気配管入口との間に前記主蒸気入口手前に配置した蒸
気の上下折流手段を介して配置したことを特徴とする特
許請求の範囲第1項に記載の沸騰水型原子炉。3. The hollow region is arranged between a steam-water separator in a nuclear reactor and an inlet of a main steam pipe via a vertical flow diverting means for steam arranged in front of the main steam inlet. The boiling water nuclear reactor according to claim 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61171610A JPH077091B2 (en) | 1986-07-23 | 1986-07-23 | Boiling water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61171610A JPH077091B2 (en) | 1986-07-23 | 1986-07-23 | Boiling water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6329294A JPS6329294A (en) | 1988-02-06 |
| JPH077091B2 true JPH077091B2 (en) | 1995-01-30 |
Family
ID=15926360
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61171610A Expired - Lifetime JPH077091B2 (en) | 1986-07-23 | 1986-07-23 | Boiling water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH077091B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5517839B2 (en) * | 2010-08-30 | 2014-06-11 | 日立Geニュークリア・エナジー株式会社 | Steam dryer and boiling water nuclear plant |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61134693A (en) * | 1984-12-06 | 1986-06-21 | 株式会社東芝 | Boiling water type reactor |
-
1986
- 1986-07-23 JP JP61171610A patent/JPH077091B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6329294A (en) | 1988-02-06 |
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