JP3422222B2 - Boiling water reactor - Google Patents
Boiling water reactorInfo
- Publication number
- JP3422222B2 JP3422222B2 JP17351597A JP17351597A JP3422222B2 JP 3422222 B2 JP3422222 B2 JP 3422222B2 JP 17351597 A JP17351597 A JP 17351597A JP 17351597 A JP17351597 A JP 17351597A JP 3422222 B2 JP3422222 B2 JP 3422222B2
- Authority
- JP
- Japan
- Prior art keywords
- guide rod
- reactor
- pressure vessel
- reactor pressure
- upper guide
- 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 - Fee Related
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
【０００１】
【発明の属する技術分野】本発明は、構造物を搬入・搬
出するための案内棒を有する原子炉圧力容器に関する。
【０００２】
【従来の技術】従来の一次冷却水再循環ポンプ内蔵型原
子炉内部構造と上部案内棒の構造を図８〜図１０により
説明する。
【０００３】図９は従来の原子炉再循環ポンプ内蔵型原
子炉構造の全体を表す縦断面図であり、図１０はそのＩ
−Ｉ水平断面図である。ここで水平断面図に関しては、
原子炉内の構造物である蒸気乾燥機１０と、シュラウド
ヘッド１１および気水分離器１２と、炉心１３を省略し
て示している。又、図９に示すように、同じく原子炉内
の構造物であるシュラウド１４と原子炉圧力容器１５と
の間の環状部分に、再循環ポンプ１６が設置されてい
る。また、主蒸気ノズル１７は途中が絞られた断面形状
を有しており、上蓋１９内部と絞り部との差圧を計測す
ることにより、原子炉運転中の主蒸気の流量を計測でき
る構造となっている。
【０００４】原子炉の定期点検時には、原子炉内部の燃
料の交換や、原子炉内部の点検を行うために、上蓋１９
を取り外した後、蒸気乾燥器１０，気水分離器１２、及
びシュラウドヘッド１１をそれぞれ取外す。定期点検後
は、上記の逆の順序でそれぞれ取り付けを行う。再循環
ポンプ１６も原子炉の定期点検時に点検のために、原子
炉圧力容器内に搬入した引き上げ装置により再循環ポン
プ１６を支持させて真上に引き上げ、引き上げ途中に引
き上げ装置ごと周方向に水平移動させて引き上げ装置で
支持した再循環ポンプ１６を上部格子板２０の切り欠き
部２１の真上に位置させてからその切り欠き部２１を通
過させて引き上げられる。再循環ポンプ１６の点検後は
上記の逆の手順で据え付けられる。
【０００５】上部案内棒１は、上記作業のうち、重量物
である蒸気乾燥器１０及びシュラウドヘッド１１および
気水分離器１２の取り外し、取り付けを行う際の位置決
めおよびガイドを行う役目をするものである。従来の案
内棒は図８に示すような構造をしており図１０の原子炉
圧力容器１５内に１８０°間隔で２箇所、主蒸気ノズル
１７近傍に、その一部を着脱自由に取り付ける。具体的
には案内棒は、定検時に案内棒の中心と圧力容器の中心
とを結ぶ直線と主蒸気ノズルの中心線との成す角度θが
９°となるように取り付ける。θを９°の位置にする理
由は前述した再循環ポンプの点検時の引き上げの際に切
り欠き部２１への水平移動のための取り扱い性や視野性
を考慮したためである。
【０００６】定期点検時の前記蒸気乾燥器１０及びシュ
ラウドヘッド１１および気水分離器１２の取り外し前に
上部案内棒を上部ブラケット２と下部ブラケット３とに
取り付けて、定期点検後、前記蒸気乾燥器及びシュラウ
ドヘッド取り付け後に取り外し、原子炉運転中は原子炉
圧力容器１５外で保管されていた。
【０００７】以上説明した一次冷却材再循環ポンプ内蔵
型原子炉の従来技術の公知例としては、特開昭57−8679
2号及び特公平3−70799 号がある。また取外し可能型案
内棒の構造に関する公知例としては、特開平2−126766
号がある。
【０００８】
【発明が解決しようとする課題】上記従来技術は、原子
炉の定期点検時に上部案内棒の取り付け、取り外し作業
が必要であったため、定検期間の短縮，合理化が難しか
った。
【０００９】又、原子炉運転中に原子炉圧力容器の主蒸
気ノズル近傍に上部案内棒を設置する場合に、その上部
案内棒の位置如何によっては主蒸気流量の計測に支障を
きたすことが考えられた。
【００１０】本発明の目的は、主蒸気流量の計測制度を
向上でき、かつ定検期間を短縮できる原子炉を提供する
ことにある。
【００１１】
【課題を解決するための手段】上記目的を達成するため
に請求項１では、主蒸気ノズルを有する原子炉圧力容器
と、原子炉圧力容器内に設置されたシュラウドヘッドと
を備えた沸騰水型原子炉において、原子炉圧力容器内に
構造物を搬入・搬出するためのガイドとなる上部案内棒
を原子炉運転中においてもシュラウドヘッドの側壁と原
子炉圧力容器の間に設置し、原子炉圧力容器水平断面に
おいて、上部案内棒の中心と原子炉圧力容器の中心とを
結ぶ直線と、主蒸気ノズルの中心線との成す角度が９°
以上12°以下になるように上部案内棒をシュラウドヘッ
ド側壁と原子炉圧力容器の間に設置した。
【００１２】θが９°以上のところに上部案内棒を原子
炉運転中において設置することで原子炉運転中の主蒸気
流量の計測に支障をきたすことなく、その計測精度が向
上する。またθを１２°以下にすることで定検時に、保
守点検のために再循環ポンプを原子炉圧力容器から取り
出す際において、再循環ポンプと上部案内棒との干渉を
避けることができる。従って、定検期間中においても上
部案内棒を原子炉圧力容器内に設置した状態で再循環ポ
ンプの保守点検が可能となる。
【００１３】このため、従来行われていた案内棒の原子
炉圧力容器内への取付け作業及び取外し作業が不要とな
り、定検期間が短縮出来る。
【００１４】また、上部案内棒は、原子炉圧力容器内壁
の高さ方向に設置された上部ブラケット及び下部ブラケ
ットを介して設置されており、案内管の長さは、下部ブ
ラケット上面から上部ブラケット下面までの距離に比べ
て短くした。原子炉運転中と原子炉停止中の温度差およ
び原子炉圧力容器と上部案内棒との線熱膨張係数の差に
よる案内棒の相対伸びを吸収できるため、上部案内棒を
原子炉圧力容器内に常設することができる。
【００１５】
【発明の実施の形態】以下、本発明の実施例を図５〜図
７により説明する。
【００１６】図６は本発明の一実施例である上部案内棒
の配置を示す縦断面図である。また図７は、図６のＩ−
Ｉ断面図である。ただし、蒸気乾燥器１０と、シュラウ
ドヘッド１１および気水分離器１２と、炉心１３は省略
して示している。図６に示すように、シュラウド１４と
原子炉圧力容器１５との環状部に、原子炉内蔵型の再循
環ポンプ１６が設置されている。また、主蒸気ノズル１
７は途中で口径が絞られた形状を有しており、原子炉運
転中の主蒸気の流量を計測できる構造となっている。こ
こで上部案内棒１の配置は、上部案内棒１が主蒸気ノズ
ル１７近傍にあることによる流れの乱れにより、運転中
の主蒸気の流量の計測に支障をきたさないように、主蒸
気ノズル１７中心と、その近傍に位置する前記上部案内
棒中心と原子炉圧力容器１５中心とがなす角度θが９°
以上となるようにし、上部案内棒１近傍の再循環ポンプ
１６の点検のために再循環ポンプ１６を引き上げる際の
取扱性や視野性に支障をきたさないように、前記角度θ
が１２°以下となるように、シュラウドヘッド１１の側
壁６と原子炉圧力容器１５との間に設置する。ここで、
上部案内棒は圧力容器内壁に設置されてあるブラケット
２，３等に取り付ける。
【００１７】主蒸気ノズル１７での蒸気流量の計測は、
Ｑを蒸気重量流量，αを流量係数，εを膨張補正係数，
ｄを主蒸気ノズル１７の断面絞り部の径，ΔＰを上蓋１
９内部と主蒸気ノズル１７断面絞り部との差圧，ρを蒸
気の密度とすると下式に基づき、前記を計測することに
より蒸気重量流量を算出できる。
【００１８】
【数１】
【００１９】ここで、蒸気の流動に関して影響するの
は、膨張補正係数εである。図５は、縦軸を膨張補正係
数εとし、横軸を上蓋１９内部と主蒸気ノズル１７断面
絞り部との差圧ΔＰを上蓋１９内部の差圧Ｐで除した比
差圧ΔＰ／Ｐとした場合に、上部案内棒１がない状態で
の理論値を実線で示し、上部案内棒１がない状態での実
験値のベストフィットカーブを一点鎖線で示している。
又、点線は上部案内棒１が、主蒸気ノズル１７中心と原
子炉圧力容器１５の中心を結ぶ直線と、その近傍に位置
する前記上部案内棒中心と原子炉圧力容器１５中心を結
ぶ直線とがなす角度θが９°となるように設置した状態
での実験値のベストフィットカーブである。図５から明
らかなように原子炉の実際の使用範囲では、上部案内棒
がない場合もある場合も実験値は理論値の±１％以内で
あり両者の相違はほとんどないことが示されている。ま
た角度を大きくしていけば、上部案内棒による流れの乱
れの下流側への影響はさらに小さくなっていくことは明
白である。しかし、θを12°以上にすると再循環ポンプ
などの構造物の取り出し、据え付けの際に上部案内棒が
支障をきたすことになるので、θは９°以上１２°以下
が望ましい。
【００２０】図１は、本発明の一実施例を示す上部案内
棒の構造であり、図２は図１のＩ−Ｉ断面図、図３は図
１のＩＩ−ＩＩ矢視図である。また図４は図１の鳥観図
である。図１において、上部案内棒１は、パイプ状の構
造物であり、上部ブラケット２下面と下部ブラケット３
との間の長さより短尺となっている。上部案内棒１の上
端部および下端部にはネジ穴が設けられている。固定プ
ラグ４は上部、下部共にネジ構造となっており、上部ネ
ジは下部ブラケット３の穴を通り上部案内棒１の下端部
ネジ穴に締結し、下部ブラケット３を挟み込み固定され
る。固定ボルト５は上部ブラケット２の穴を通り上部案
内棒１の上端部ネジ穴に締結される。ここで、上部案内
棒１は、上部ブラケット２下面と下部ブラケット３上面
との間の長さより短尺となっているため、上部案内棒１
上面と上部ブラケット２下面とには隙間が形成される。
キャップ７は、側面に上部ブラケット２を挿入するため
のスリットを有するパイプ状の構造物であり、固定ボル
ト５，上部ブラケット２円筒部を覆っている。又キャッ
プ７の下端は上部案内棒１上面に溶接等により固定され
る。下部案内棒８は上端部にネジ穴を有しプラグの下部
ネジに締結される。
【００２１】以上の実施例によれば、原子炉圧力容器水
平断面で上部案内棒の中心と原子炉圧力容器の中心とを
結ぶ直線と、主蒸気ノズルの中心線との成す角度θを９
°以上のところに上部案内棒を設置することで主蒸気流
量の計測に支障をきたすことがなく、又θを１２°以下
にすることで定検時における再循環ポンプ等の構造物の
取り出し、据え付けの際に支障をきたすことがない。
【００２２】また、上部案内棒を原子炉圧力容器内壁の
高さ方向に設置された上部ブラケット及び下部ブラケッ
トを介して設置し、上部案内棒の長さを、上部ブラケッ
ト下面から下部ブラケット上面との間の距離に比べて短
くすることで原子炉運転中と原子炉停止中の温度差およ
び原子炉圧力容器と上部案内棒との線熱膨張係数の差に
よる案内棒の相対伸びを吸収できるため、上部案内棒を
原子炉圧力容器内に設置することができる。
【００２３】
【発明の効果】本発明によれば、上部案内棒の取り付け
取り外し作業が不要になるので、沸騰水型原子炉におけ
る定検期間が短縮される。Description: BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor pressure vessel having a guide rod for carrying in / out a structure. 2. Description of the Related Art The internal structure of a conventional reactor with a built-in primary cooling water recirculation pump and the structure of an upper guide rod will be described with reference to FIGS. FIG. 9 is a longitudinal sectional view showing the entire structure of a conventional reactor with a built-in reactor recirculation pump, and FIG.
-I is a horizontal sectional view. Here, regarding the horizontal sectional view,
A steam dryer 10 as a structure in a nuclear reactor, a shroud head 11, a steam separator 12, and a reactor core 13 are omitted. As shown in FIG. 9, a recirculation pump 16 is provided in an annular portion between a shroud 14, which is also a structure in the reactor, and a reactor pressure vessel 15. Further, the main steam nozzle 17 has a cross-sectional shape in which the middle is throttled, and has a structure capable of measuring the flow rate of the main steam during the operation of the reactor by measuring the differential pressure between the upper lid 19 and the throttle portion. Has become. At the time of periodic inspection of the reactor, the upper cover 19 is used to exchange fuel inside the reactor and to inspect the inside of the reactor.
, The steam dryer 10, the steam separator 12, and the shroud head 11 are removed. After the periodic inspection, install each in the reverse order. The recirculation pump 16 is also lifted directly above by supporting the recirculation pump 16 by a lifting device carried into the reactor pressure vessel for inspection at the time of periodic inspection of the reactor. The recirculation pump 16 that has been moved and supported by the lifting device is positioned right above the notch 21 of the upper lattice plate 20 and then pulled up through the notch 21. After the recirculation pump 16 is inspected, it is installed in the reverse procedure. The upper guide rod 1 serves to perform positioning and guiding when removing and attaching the steam dryer 10, the shroud head 11, and the steam separator 12, which are heavy materials, in the above operation. is there. The conventional guide rod has a structure as shown in FIG. 8, and a part thereof is freely attached and detached in the vicinity of the main steam nozzle 17 at two positions in the reactor pressure vessel 15 of FIG. Specifically, the guide rod is attached so that the angle θ between a straight line connecting the center of the guide rod and the center of the pressure vessel and the center line of the main steam nozzle during regular inspection is 9 °. The reason why θ is set to the position of 9 ° is that the handling and the visibility for the horizontal movement to the notch 21 are taken into consideration when the recirculation pump is pulled up for inspection. Before removing the steam dryer 10, the shroud head 11, and the steam separator 12 at the time of periodic inspection.
The upper guide rod was attached to the upper bracket 2 and the lower bracket 3, and was removed after the periodic inspection and after the attachment of the steam dryer and the shroud head, and was stored outside the reactor pressure vessel 15 during the operation of the reactor. [0007] A known example of the above-described prior art reactor with a built-in primary coolant recirculation pump is disclosed in Japanese Patent Application Laid-Open No. 57-8679.
No. 2 and Tokuhei 3-70799. Further, as a known example of the structure of the removable type guide rod, see Japanese Patent Application Laid-Open No. 2-126766.
There is a number. [0008] In the above prior art, it was difficult to shorten and rationalize the regular inspection period because it was necessary to install and remove the upper guide rod during the periodic inspection of the reactor. Further, when the upper guide rod is installed near the main steam nozzle of the reactor pressure vessel during the operation of the reactor, the measurement of the main steam flow rate may be hindered depending on the position of the upper guide rod. It was thought to come. An object of the present invention is to provide a nuclear reactor capable of improving the measurement system of the main steam flow rate and shortening the regular inspection period. In order to achieve the above object, according to the present invention, a reactor pressure vessel having a main steam nozzle and a shroud head installed in the reactor pressure vessel are provided. In a boiling water reactor, an upper guide rod serving as a guide for loading and unloading structures into and from the reactor pressure vessel is installed between the side wall of the shroud head and the reactor pressure vessel even during reactor operation, In the horizontal cross section of the reactor pressure vessel, the angle between the straight line connecting the center of the upper guide rod and the center of the reactor pressure vessel and the center line of the main steam nozzle is 9 °.
The upper guide rod was set between the side wall of the shroud head and the reactor pressure vessel so as to be at least 12 ° or less. By installing the upper guide rod at a position where θ is 9 ° or more during the operation of the reactor, the measurement accuracy is improved without hindering the measurement of the main steam flow rate during the operation of the reactor. When θ is set to 12 ° or less, interference between the recirculation pump and the upper guide rod can be avoided when the recirculation pump is taken out of the reactor pressure vessel for maintenance and inspection at the time of regular inspection. Therefore, above even during the outage period
Maintenance and inspection of the recirculation pump can be performed with the section guide rod installed in the reactor pressure vessel. For this reason, the work of mounting and removing the guide rod in the reactor pressure vessel, which has been conventionally performed, becomes unnecessary, and the period of regular inspection can be shortened. The upper guide rod is installed via an upper bracket and a lower bracket which are installed in the height direction of the inner wall of the reactor pressure vessel. The length of the guide tube is from the upper surface of the lower bracket to the lower surface of the upper bracket. Shorter than the distance to. Since the relative elongation of the guide rod due to the temperature difference between the reactor operation and the reactor shutdown and the difference in linear thermal expansion coefficient between the reactor pressure vessel and the upper guide rod can be absorbed, the upper guide rod is placed inside the reactor pressure vessel. Can be permanent. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS. FIG. 6 is a longitudinal sectional view showing the arrangement of the upper guide bar according to one embodiment of the present invention. Also, FIG.
It is I sectional drawing. However, the steam dryer 10, the shroud head 11, the steam-water separator 12, and the core 13 are omitted. As shown in FIG. 6, a recirculation pump 16 of a built-in reactor type is installed in an annular portion between the shroud 14 and the reactor pressure vessel 15. The main steam nozzle 1
Reference numeral 7 has a shape whose diameter is reduced in the middle, and has a structure capable of measuring the flow rate of main steam during operation of the reactor. Wherein the arrangement of the upper guide rod 1, the flow by the upper guide rod 1 is in the vicinity the main steam nozzle 17 turbulence, so as not to disturb the measurement of the flow rate of the main steam during operation, a main steam nozzle 17 The angle θ formed by the center, the center of the upper guide rod located in the vicinity thereof, and the center of the reactor pressure vessel 15 is 9 °.
As described above, the angle θ is adjusted so as not to impair the handling and visibility when the recirculation pump 16 is pulled up for inspection of the recirculation pump 16 near the upper guide rod 1.
Is set between the side wall 6 of the shroud head 11 and the reactor pressure vessel 15 so as to be 12 ° or less. here,
The upper guide rod is attached to brackets 2, 3 and the like provided on the inner wall of the pressure vessel. The measurement of the steam flow rate at the main steam nozzle 17 is as follows.
Q is the steam mass flow rate, α is the flow coefficient, ε is the expansion correction coefficient,
d is the diameter of the cross section of the main steam nozzle 17 and ΔP is the upper lid 1
Assuming that the pressure difference between the inside of the nozzle 9 and the narrowed section of the main steam nozzle 17 is ρ, the density of the steam, the steam weight flow rate can be calculated by measuring the above based on the following equation. ## EQU1 ## Here, what affects the steam flow is the expansion correction coefficient ε. In FIG. 5, the vertical axis represents the expansion correction coefficient ε, and the horizontal axis represents the specific pressure difference ΔP / P obtained by dividing the pressure difference ΔP between the inside of the upper lid 19 and the narrowed section of the main steam nozzle 17 by the differential pressure P inside the upper lid 19. In this case, the theoretical value without the upper guide rod 1 is shown by a solid line, and the best fit curve of the experimental value without the upper guide rod 1 is shown by a dashed line.
Also, the dotted line the upper guide bar 1, and a straight line connecting the centers of the main steam nozzle 17 center and the reactor pressure vessel 15, a straight line connecting the upper guide rod center and the reactor pressure vessel 15 center located in the vicinity thereof It is a best-fit curve of an experimental value in a state where the angle θ is 9 °. As is clear from FIG. 5, in the actual use range of the nuclear reactor, the experimental value is within ± 1% of the theoretical value even when the upper guide rod is not provided, and there is little difference between the two. . It is clear that the effect of the upper guide rod on the downstream side is further reduced as the angle is increased. However, if θ is set to 12 ° or more, the upper guide rod may interfere with taking out and installing a structure such as a recirculation pump. Therefore, θ is preferably 9 ° to 12 °. FIG. 1 shows the structure of an upper guide bar according to an embodiment of the present invention. FIG. 2 is a sectional view taken along line II of FIG. 1, and FIG. 3 is a view taken along line II-II of FIG. FIG. 4 is a bird's-eye view of FIG. In FIG. 1, an upper guide rod 1 is a pipe-shaped structure, and a lower surface of an upper bracket 2 and a lower bracket 3
Is shorter than the length between Screw holes are provided at the upper end and the lower end of the upper guide rod 1. The fixing plug 4 has a screw structure in both the upper part and the lower part. The upper screw passes through the hole of the lower bracket 3 and is fastened to the screw hole at the lower end of the upper guide rod 1 so that the lower bracket 3 is sandwiched and fixed. Fixing bolt 5 is fastened to the holes of the top bracket 2 to the upper portion screw holes as the upper draft <br/> the rod 1. Here, since the upper guide rod 1 is shorter than the length between the lower surface of the upper bracket 2 and the upper surface of the lower bracket 3, the upper guide rod 1
A gap is formed between the upper surface and the lower surface of the upper bracket 2.
The cap 7 is a pipe-shaped structure having a slit for inserting the upper bracket 2 on a side surface, and covers the fixing bolt 5 and the cylindrical portion of the upper bracket 2. The lower end of the cap 7 is fixed to the upper surface of the upper guide rod 1 by welding or the like. The lower guide rod 8 has a screw hole at the upper end and is fastened to the lower screw of the plug. According to the above embodiment, the angle .theta. Between the straight line connecting the center of the upper guide rod and the center of the reactor pressure vessel and the center line of the main steam nozzle in the horizontal cross section of the reactor pressure vessel is 9 degrees.
By installing the upper guide bar at a temperature of more than °, there is no problem in the measurement of the main steam flow, and by making θ less than 12 °, removal of structures such as the recirculation pump at the time of regular inspection, There is no hindrance during installation. Also, the upper guide rod is installed via an upper bracket and a lower bracket which are installed in the height direction of the inner wall of the reactor pressure vessel, and the length of the upper guide rod is adjusted from the lower surface of the upper bracket to the upper surface of the lower bracket. By shortening the distance between the reactor and the reactor, the relative elongation of the guide rod due to the temperature difference between the reactor operating and the reactor shutdown and the difference in linear thermal expansion coefficient between the reactor pressure vessel and the upper guide rod can be absorbed. An upper guide rod can be installed in the reactor pressure vessel. According to the present invention, since the work of attaching and detaching the upper guide rod becomes unnecessary, the regular inspection period in the boiling water reactor is shortened.
【図面の簡単な説明】
【図１】本発明による上部案内棒構造図。
【図２】図１のＩ−Ｉ断面図。
【図３】図１のII−II矢視図。
【図４】図１の鳥瞰図。
【図５】本発明と従来構造との実験値の比較図。
【図６】本発明を用いた原子炉縦断面図。
【図７】図６のＩ−Ｉ断面図。
【図８】従来の上部案内棒構造図。
【図９】従来の上部案内棒を用いた原子炉縦断面図。
【図１０】図９のＩ−Ｉ断面図。
【符号の説明】
１…上部案内棒、２…上部ブラケット、３…下部ブラケ
ット、４…固定プラグ、５…固定ボルト、６…シュラウ
ドヘッド側壁、７…キャップ、８…下部案内棒、９…フ
ランジ、１０…蒸気乾燥器、１１…シュラウドヘッド、
１２…気水分離器、１３…炉心、１４…シュラウド、１
５…原子炉圧力容器、１６…再循環ポンプ、１７…主蒸
気ノズル、１９…上蓋、２０…上部格子板、２１…切り
欠き部。BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a structural diagram of an upper guide rod according to the present invention. FIG. 2 is a sectional view taken along line II of FIG. 1; FIG. 3 is a view taken in the direction of arrows II-II in FIG. 1; FIG. 4 is a bird's-eye view of FIG. 1; FIG. 5 is a comparison diagram of experimental values between the present invention and a conventional structure. FIG. 6 is a longitudinal sectional view of a reactor using the present invention. FIG. 7 is a sectional view taken along the line II of FIG. 6; FIG. 8 is a structural diagram of a conventional upper guide rod. FIG. 9 is a longitudinal sectional view of a nuclear reactor using a conventional upper guide rod. FIG. 10 is a sectional view taken along line II of FIG. 9; [Description of Signs] 1 ... Upper guide rod, 2 ... Upper bracket, 3 ... Lower bracket, 4 ... Fixing plug, 5 ... Fixing bolt, 6 ... Shroud head side wall, 7 ... Cap, 8 ... Lower guide rod, 9 ... Flange 10, steam dryer, 11 shroud head,
12: steam-water separator, 13: core, 14: shroud, 1
5: Reactor pressure vessel, 16: Recirculation pump, 17: Main steam nozzle, 19: Upper lid, 20: Upper lattice plate, 21: Notch.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 松浦 正義 茨城県日立市幸町三丁目１番１号 株式 会社 日立製作所 日立工場内 (56)参考文献 特開 平２−126766（ＪＰ，Ａ) 特開 平８−327769（ＪＰ，Ａ) 特開 平６−273569（ＪＰ，Ａ) 特開 平１−285898（ＪＰ，Ａ) (58)調査した分野(Int.Cl.7，ＤＢ名) G21C 13/00 ──────────────────────────────────────────────────続 き Continuing from the front page (72) Inventor Masayoshi Matsuura 3-1-1, Sakaimachi, Hitachi-shi, Ibaraki Hitachi, Ltd. Hitachi Plant (56) Reference JP-A-2-126766 (JP, A) JP-A-8-327769 (JP, A) JP-A-6-273569 (JP, A) JP-A-1-285988 (JP, A) (58) Fields investigated (Int. Cl. 7 , DB name) G21C13 / 00
Claims (1)
前記原子炉圧力容器内に設置されたシュラウドヘッドと
を備えた沸騰水型原子炉において、 前記原子炉圧力容器内に構造物を搬入・搬出するための
ガイドとなる上部案内棒を原子炉運転中においても前記
シュラウドヘッドの側壁と前記原子炉圧力容器の間に設
置し、前記原子炉圧力容器水平断面における、前記上部
案内棒の中心と前記原子炉圧力容器の中心とを結ぶ直線
と、前記主蒸気ノズルの中心線との成す角度が９°以上
１２°以下になっていると共に、前記上部案内棒は、前
記原子炉圧力容器内壁の高さ方向に設置された上部ブラ
ケット及び下部ブラケットを介して設置されており、前
記上部案内棒の長さは、前記下部ブラケット上面から前
記上部ブラケット下面までの距離に比べて短いことを特
徴とする沸騰水型原子炉。(57) [Claim 1] A reactor pressure vessel having a main steam nozzle,
In a boiling water reactor having a shroud head installed in the reactor pressure vessel, an upper guide rod serving as a guide for loading / unloading a structure into / from the reactor pressure vessel is operated during reactor operation. also installed between the reactor pressure vessel and a side wall of the shroud head in, definitive in the reactor pressure vessel a horizontal cross-section, connecting the center of said reactor pressure vessel of the upper <br/> guide bar The angle between the straight line and the center line of the main steam nozzle is 9 ° or more and 12 ° or less, and the upper guide rod is
The upper bra installed in the height direction of the inner wall of the reactor pressure vessel
It is installed via a bracket and lower bracket,
The length of the upper guide rod should be
A boiling water reactor characterized by being shorter than the distance to the lower surface of the upper bracket .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17351597A JP3422222B2 (en) | 1997-06-30 | 1997-06-30 | Boiling water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17351597A JP3422222B2 (en) | 1997-06-30 | 1997-06-30 | Boiling water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH1123772A JPH1123772A (en) | 1999-01-29 |
| JP3422222B2 true JP3422222B2 (en) | 2003-06-30 |
Family
ID=15961963
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP17351597A Expired - Fee Related JP3422222B2 (en) | 1997-06-30 | 1997-06-30 | Boiling water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3422222B2 (en) |
-
1997
- 1997-06-30 JP JP17351597A patent/JP3422222B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH1123772A (en) | 1999-01-29 |
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