JPS6145514Y2 - - Google Patents
Info
- Publication number
- JPS6145514Y2 JPS6145514Y2 JP1980007095U JP709580U JPS6145514Y2 JP S6145514 Y2 JPS6145514 Y2 JP S6145514Y2 JP 1980007095 U JP1980007095 U JP 1980007095U JP 709580 U JP709580 U JP 709580U JP S6145514 Y2 JPS6145514 Y2 JP S6145514Y2
- Authority
- JP
- Japan
- Prior art keywords
- support plate
- core support
- stud
- core
- shroud
- 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
Links
- 229910001026 inconel Inorganic materials 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- 238000006073 displacement reaction Methods 0.000 claims 1
- 239000000446 fuel Substances 0.000 description 7
- 238000009434 installation Methods 0.000 description 6
- 238000000034 method Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 230000005855 radiation 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【考案の詳細な説明】
本案は沸騰水形原子炉圧力容器の特に原子炉内
炉心支持板に関するものである。[Detailed Description of the Invention] The present invention relates to a core support plate in a boiling water reactor pressure vessel, particularly in a nuclear reactor.
第１図から第３図は従来の原子炉心支持板構造
を示したもので、７は気水分離器、８は蒸気乾燥
器、９は制御棒、１０は燃料集合体、１１はジエ
ツトポンプを示し、燃料集合体１０は原子炉圧力
容器１内にあつて、炉心支持板５及び上部格子板
６で支えられ、更に炉心支持板５と上部格子板６
は炉心シユラウド２ならびにシユラウドサポート
３によつて支持してある。 Figures 1 to 3 show the structure of a conventional nuclear reactor core support plate, with reference numeral 7 indicating a steam separator, 8 indicating a steam dryer, 9 indicating a control rod, 10 indicating a fuel assembly, and 11 indicating a jet pump. , the fuel assembly 10 is located in the reactor pressure vessel 1 and is supported by a core support plate 5 and an upper grid plate 6, and is further supported by a core support plate 5 and an upper grid plate 6.
is supported by a core shroud 2 and a shroud support 3.
炉心支持板５は燃料集合体１０の位置決めと、
地震時の横方向の移動を制限するために、厳しい
寸法精度が要求されている。かつ、各々４体の燃
料集合体１０の中心部に制御棒９が配置されてお
り、制御棒９の円滑な操作が行なえるように、炉
心支持板５の現地据付は、第２図に示すように、
原子炉圧力容器１の下部に置されているCRD
（制御棒駆動機構）スタブの中心X1と炉心支持板
５の穴の中心X2が垂直線上に一致するように炉
心支持板５の据付位置を調整する。 The core support plate 5 is used for positioning the fuel assembly 10,
Strict dimensional accuracy is required to limit lateral movement during an earthquake. In addition, the control rods 9 are arranged at the center of each of the four fuel assemblies 10, and in order to ensure smooth operation of the control rods 9, the on-site installation of the core support plate 5 is as shown in FIG. like,
CRD placed at the bottom of reactor pressure vessel 1
(Control rod drive mechanism) Adjust the installation position of the core support plate 5 so that the center X1 of the stub and the center X2 of the hole in the core support plate 5 are aligned on a vertical line.
しかるのち、第３図に示すように、スタツド１
３、ナツト１４、球面ワツシヤ１５により、炉心
支持板５を締付固定する。 Afterwards, as shown in Figure 3, the stud 1
3. Tighten and fix the core support plate 5 using the nuts 14 and spherical washers 15.
この方法だと、地震時に燃料集合体１０の反力
が炉心支持板５に加わつた時、第３図の二点鎖線
で示すように、炉心支持板５が横方向に移動する
可能性がある。この横ずれ防止のため、過大なト
ルクでスタツド１３を締付け、炉心支持板５の下
面とシユラウド２のフランジ上面のまさつ力が抵
抗するようになつているが、炉心支持板５の上面
の変形を完全に防止することは出来ない。また、
炉心支持板５は通常運転時、冷却材の流れによつ
て、上向きの力を受けるが、この力に比し、横ず
れ防止のため、スタツド１３の締付力は約４倍以
上必要となり、スタツド１３および炉心支持板５
に常時過大な応力を発生せしめている。 With this method, when the reaction force of the fuel assembly 10 is applied to the core support plate 5 during an earthquake, there is a possibility that the core support plate 5 will move laterally, as shown by the two-dot chain line in FIG. . In order to prevent this lateral shift, the studs 13 are tightened with excessive torque so that the force exerted by the lower surface of the core support plate 5 and the upper surface of the flange of the shroud 2 is resisted. It cannot be completely prevented. Also,
During normal operation, the core support plate 5 is subjected to an upward force due to the flow of coolant, but compared to this force, the tightening force of the studs 13 is approximately four times greater than this force to prevent lateral slippage. 13 and core support plate 5
Excessive stress is constantly generated on the
一方、最近、原子炉炉内機器の点検および原子
炉の圧力容器底部のクラツド除去などで、炉心支
持板５を取外す必要性が出て来ている。 On the other hand, recently, it has become necessary to remove the core support plate 5 for inspection of internal components of a nuclear reactor, removal of crud from the bottom of a pressure vessel of a nuclear reactor, and the like.
そのために、炉心支持板５は取外しおよび再据
付が容易であることが要求される。 Therefore, the core support plate 5 is required to be easy to remove and reinstall.
スタツド１３は炉心支持板５が横ずれした場合
スタツド１３に曲げ応力が発生するのを防ぐため
に、球面ワツシヤ１５を使用しており、球面ワツ
シヤ１５とシユラウド２のフランジは溶接などに
より固定することは不可である。従つて、従来構
造（第３図）の炉心支持板５を運転後に取外す時
は、高線量であるため、作業はすべて遠隔操作と
なり、先ず、スタツド１３の下部を回転止めし
て、かつ、スタツド１３の落下を防止する特殊工
具を装着し、上部ナツト１４をゆるめる。スタツ
ド１３は炉心支持板５の下方向に取出し、炉外に
移動する必要があり、作業に慎重を期し、困難性
を伴なう。 The stud 13 uses a spherical washer 15 in order to prevent bending stress from occurring in the stud 13 when the core support plate 5 shifts laterally, and the flange of the spherical washer 15 and the shroud 2 cannot be fixed by welding or the like. It is. Therefore, when removing the core support plate 5 of the conventional structure (Fig. 3) after operation, all work must be done remotely due to the high radiation dose.First, the lower part of the stud 13 must be stopped from rotating, and Attach a special tool to prevent 13 from falling and loosen upper nut 14. The studs 13 must be taken out below the core support plate 5 and moved out of the reactor, which requires careful and difficult work.
また、炉心支持板５を再据付する時は、上記の
逆手順となるが、その前に、第２図に示す炉心支
持板５の据付位置決めを実施する必要があり、遠
隔操作では、所定の据付位置決めの精度向上は期
待できない。 In addition, when reinstalling the core support plate 5, the above procedure is reversed, but before that, it is necessary to determine the installation position of the core support plate 5 as shown in FIG. Improvements in the accuracy of installation positioning cannot be expected.
本案の目的は、炉心支持板の取出し、再据付を
容易ならしめ、炉心支持板の地震時の横方向のず
れを防止し、かつ、スタツドの応力を低減させる
ことにある。 The purpose of this proposal is to facilitate the removal and reinstallation of the core support plate, to prevent the core support plate from shifting in the lateral direction during an earthquake, and to reduce the stress on the studs.
本案は炉心支持板を固定かつ位置決めするスタ
ツド（インコネル製）とクサビ及びストツパを組
合せた構造を用いるとによつて、上記の目的を達
成することができるものである。 The present invention achieves the above object by using a structure that combines a stud (made of Inconel), a wedge, and a stopper for fixing and positioning the core support plate.
次に、本案に係る高耐震型炉心支持板の実施例
を第４図について説明する。 Next, an embodiment of the highly seismic core support plate according to the present invention will be described with reference to FIG. 4.
スタツド１６の先端に近い部分にはテーパが付
いており、炉心支持板５のテーパ穴にはまり合
う。スタツド１６の下方には、第２図に示す炉心
支持板５の据付位置決め後、スタツド１６が所定
の位置に配置されるように、偏心スリーブ１８を
挿入し、シユラウド２のフランジに溶接固定す
る。スタツド１６の上部テーパと炉心支持板５の
テーパ穴が密着するように調整し、上部のナツト
１７を回転させ偏心スリーブ１８とスタツド１６
に溶接固定する。この状態でスタツド１６に完全
に固定かつ位置決めされたことになる。 The stud 16 has a tapered portion near the tip and fits into a tapered hole in the core support plate 5. After the core support plate 5 is installed and positioned as shown in FIG. 2, an eccentric sleeve 18 is inserted below the stud 16 so that the stud 16 is placed in a predetermined position, and is welded and fixed to the flange of the shroud 2. Adjust so that the upper taper of the stud 16 and the taper hole of the core support plate 5 are in close contact, and rotate the upper nut 17 to remove the eccentric sleeve 18 and the stud 16.
Fixed by welding. In this state, it is completely fixed and positioned on the stud 16.
さらに、クサビ１９をシユラウド２と炉心支持
板５との間に挿入し、ストツパ２０を介して、上
部ナツト１７によりスタツド１６を締付固定す
る。スタツド１６は熱膨脹係数の小さいインコネ
ル製（従来はステンレス製）であるため、炉心支
持板５はステンレス製のため、原子炉運転により
温度上昇した場合、熱膨脹差により炉心支持板５
は締付けられる。したがつて、スタツド１６の初
期締付力は少なくてよいので、スタツド１６の締
付および取出し時に、過大なトルクを必要としな
いので、作業性が向上する。また、クサビ１９を
配置したことにより炉心支持板５の地震時の横ず
れが防止でき、燃料集合体１０の健全性が確保で
きる。また、原子炉運転後に、炉心支持板５を取
外し、再据付する場合においても、スタツド１６
は所定の位置に固定されており、スタツド１６の
上部テーパと炉心支持板５のテーパ穴がはまり合
う様に再据付を行えば、完全に炉心支持板５の据
付位置決めが可能であり、高放射線下の作業にお
いて、作業工数を大巾に低減でき、かつ工程を短
縮できる。 Furthermore, the wedge 19 is inserted between the shroud 2 and the core support plate 5, and the stud 16 is tightened and fixed by the upper nut 17 via the stopper 20. The studs 16 are made of Inconel (previously made of stainless steel), which has a small coefficient of thermal expansion, and the core support plate 5 is made of stainless steel. Therefore, when the temperature rises due to reactor operation, the core support plate 5 will change due to the difference in thermal expansion.
is tightened. Therefore, since the initial tightening force for the stud 16 may be small, excessive torque is not required when tightening and removing the stud 16, improving work efficiency. Further, by arranging the wedges 19, it is possible to prevent the core support plate 5 from shifting laterally during an earthquake, and the integrity of the fuel assembly 10 can be ensured. Also, when the core support plate 5 is removed and reinstalled after reactor operation, the studs 16
is fixed in a predetermined position, and if it is reinstalled so that the upper taper of the stud 16 fits into the taper hole of the core support plate 5, the installation position of the core support plate 5 can be completely determined. In the following work, the number of man-hours can be greatly reduced, and the process can be shortened.
第１図は原子炉の内部構造を示す断面図、第２
図は炉心支持板の据付位置決めを示す縦断面図、
第３図は第２図のＡ部詳細図で従来の炉心支持板
の固定方法を示す縦断面図、第４図は本案に係わ
る高耐震型炉心支持板の固定方法の一実施例を示
す縦断面図である。
１……原子炉圧力容器、２……炉心シユラウ
ド、３……シユラウドサポート、４……シユラウ
ドヘツド、５……炉心支持板、６……上部格子
板、７……気水分離器、８……蒸気乾燥器、９…
…制御棒、１０……燃料集合体、１１……ジエツ
トポンプ、１２……CRDスタブ、１３……スタ
ツド、１４……ナツト、１５……球面ワツシヤ、
１６……スタツド、１７……ナツト、１８……偏
心スリーブ、１９……クサビ、２０……ストツ
パ。
Figure 1 is a sectional view showing the internal structure of the reactor, Figure 2
The figure is a longitudinal sectional view showing the installation positioning of the core support plate.
Fig. 3 is a detailed view of part A in Fig. 2, and is a vertical cross-sectional view showing a conventional method of fixing a core support plate, and Fig. 4 is a longitudinal cross-sectional view showing an example of a method of fixing a highly seismic core support plate according to the present proposal. It is a front view. DESCRIPTION OF SYMBOLS 1... Reactor pressure vessel, 2... Core shroud, 3... Shroud support, 4... Shroud head, 5... Core support plate, 6... Upper grid plate, 7... Steam water separator, 8... ...Steam dryer, 9...
... Control rod, 10 ... Fuel assembly, 11 ... Jet pump, 12 ... CRD stub, 13 ... Stud, 14 ... Nut, 15 ... Spherical washer,
16... Stud, 17... Nut, 18... Eccentric sleeve, 19... Wedge, 20... Stopper.
Claims (1)
心シユラウド間に複数個のクサビを配置し、先端
部にテーパを有したインコネル製のスタツドによ
り、前記炉心支持板と炉心シユラウドを固定し、
原子炉運転により温度上昇した場合、熱膨脹差に
より前記炉心支持板を十分締付け、前記炉心支持
板の地震時の横方向ずれを防止し、かつ、前記炉
心支持板の取外しおよび再据付を容易にしたこと
を特徴とする原子炉内の高耐震型炉心支持板。 A plurality of wedges are arranged between a stainless steel core support plate and a core shroud that supports the same, and the core support plate and the core shroud are fixed with an Inconel stud having a tapered tip,
When the temperature rises due to reactor operation, the core support plate is sufficiently tightened due to the difference in thermal expansion, preventing lateral displacement of the core support plate during an earthquake, and facilitating the removal and reinstallation of the core support plate. A highly seismic core support plate for use in a nuclear reactor, which is characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1980007095U JPS6145514Y2 (en) | 1980-01-25 | 1980-01-25 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1980007095U JPS6145514Y2 (en) | 1980-01-25 | 1980-01-25 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56110392U JPS56110392U (en) | 1981-08-26 |
| JPS6145514Y2 true JPS6145514Y2 (en) | 1986-12-20 |
Family
ID=29603757
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1980007095U Expired JPS6145514Y2 (en) | 1980-01-25 | 1980-01-25 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6145514Y2 (en) |
-
1980
- 1980-01-25 JP JP1980007095U patent/JPS6145514Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56110392U (en) | 1981-08-26 |
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