JPS6357596U - - Google Patents
Info
- Publication number
- JPS6357596U JPS6357596U JP1986150221U JP15022186U JPS6357596U JP S6357596 U JPS6357596 U JP S6357596U JP 1986150221 U JP1986150221 U JP 1986150221U JP 15022186 U JP15022186 U JP 15022186U JP S6357596 U JPS6357596 U JP S6357596U
- Authority
- JP
- Japan
- Prior art keywords
- cross
- groove
- sectional area
- tie rod
- spot
- 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
- 238000003466 welding Methods 0.000 claims description 3
- 238000010521 absorption reaction Methods 0.000 claims description 2
- 239000002826 coolant Substances 0.000 claims 1
- 230000013011 mating Effects 0.000 claims 1
- 238000010586 diagram Methods 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 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
- Butt Welding And Welding Of Specific Article (AREA)
Description
第１図は本考案に係る制御棒の実施例の要部を
一部切欠して示す正面図、第２図は第１図で示す
ブレードの上部の斜視図、第３図は第１図のＡ―
Ａ矢視断面図、第４図は従来の制御棒の上部を示
す斜視図、第５図は第４図で示すブレードの上部
を一部切欠して示す正面図、第６図は溶存酸素濃
度に対する応力腐食割れ感受性の依存性を示す特
性図である。
１，１１…ブレード、２，１２…先端構造材、
３，１３…ハンドル、４，１４…中性子吸収棒、
５，１５…シース、６…連続スミ肉溶接部、７，
１７…タイロツド、８，１８…点溶接部、９，１
９…冷却孔、２０…溝。
Fig. 1 is a partially cutaway front view of the main part of the control rod according to the present invention, Fig. 2 is a perspective view of the upper part of the blade shown in Fig. 1, and Fig. 3 is the same as Fig. 1. A-
4 is a perspective view showing the upper part of a conventional control rod, 5 is a front view with a part of the upper part of the blade shown in 4 cut away, and 6 is a diagram showing the dissolved oxygen concentration. FIG. 2 is a characteristic diagram showing the dependence of stress corrosion cracking susceptibility on 1, 11... Blade, 2, 12... Tip structure material,
3,13...handle, 4,14...neutron absorption rod,
5, 15... Sheath, 6... Continuous fillet welded part, 7,
17... Tie rod, 8, 18... Spot welding part, 9, 1
9...Cooling hole, 20...Groove.
Claims (1)
を、タイロツド周りに所定形状に配列して点溶接
すると共に、これらシースの一端に先端構造材を
点溶接する原子炉用制御棒において、前記点溶接
のために前記シースの端部と重なり合う前記先端
構造材もしくはタイロツドの重ね合せ部の合せ面
に、冷却材の流れ方向に向けて一端が開口する溝
を、前記点溶接が行なわれる点溶接部以外の箇所
にて設け、この溝の凹み方向に沿う溝横断面の面
積が、この溝横断面と同一断面における前記先端
構造材の横断面積に対しては８割以下に、前記タ
イロツドの横断面積に対しては５割以下にそれぞ
れ設定されたことを特徴とする原子炉用制御棒。 In a control rod for a nuclear reactor, in which a plurality of sheaths containing a plurality of neutron absorption rods are arranged in a predetermined shape around a tie rod and spot welded, and a tip structural member is spot welded to one end of these sheaths, the spot welding is performed. For this reason, a groove with one end open in the flow direction of the coolant is provided in the mating surface of the overlapping portion of the tip structure member or tie rod that overlaps with the end of the sheath, other than the spot weld where the spot welding is performed. The cross-sectional area of the groove along the concave direction of the groove is 80% or less of the cross-sectional area of the tip structure member in the same cross-section as the groove cross-section, and the cross-sectional area of the tie rod is A control rod for a nuclear reactor is characterized in that it is set to 50% or less.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1986150221U JPS6357596U (en) | 1986-09-30 | 1986-09-30 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1986150221U JPS6357596U (en) | 1986-09-30 | 1986-09-30 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6357596U true JPS6357596U (en) | 1988-04-16 |
Family
ID=31066167
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1986150221U Pending JPS6357596U (en) | 1986-09-30 | 1986-09-30 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6357596U (en) |
-
1986
- 1986-09-30 JP JP1986150221U patent/JPS6357596U/ja active Pending
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