JPH0220957B2 - - Google Patents
Info
- Publication number
- JPH0220957B2 JPH0220957B2 JP60063223A JP6322385A JPH0220957B2 JP H0220957 B2 JPH0220957 B2 JP H0220957B2 JP 60063223 A JP60063223 A JP 60063223A JP 6322385 A JP6322385 A JP 6322385A JP H0220957 B2 JPH0220957 B2 JP H0220957B2
- Authority
- JP
- Japan
- Prior art keywords
- tapered surface
- end plug
- cladding tube
- welded
- nuclear fuel
- 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
Links
- 238000005253 cladding Methods 0.000 claims description 15
- 230000035515 penetration Effects 0.000 claims description 15
- 239000003758 nuclear fuel Substances 0.000 claims description 10
- 239000000463 material Substances 0.000 claims 1
- 238000003466 welding Methods 0.000 description 11
- 230000007547 defect Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 239000011800 void material Substances 0.000 description 3
- 230000002950 deficient Effects 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000009659 non-destructive testing Methods 0.000 description 1
- 238000000275 quality assurance Methods 0.000 description 1
- 230000000007 visual effect 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)
- Catalysts (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、溶接部分の健全性を容易かつ正確に
判定し得るようにした原子炉核燃料棒に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a nuclear reactor nuclear fuel rod in which the soundness of a welded portion can be easily and accurately determined.
一般に原子炉核燃料棒は、第４図に示すよう
に、核燃料物質１を装填した被覆管２と、この被
覆管内に配設されるばね３と、被覆管２の両端部
に嵌合される端栓４，４とを有して構成され、端
栓４と被覆管２の突合せ部はTIG溶接法等により
溶接されている。
In general, a nuclear fuel rod in a nuclear reactor, as shown in FIG. The butt portion of the end plug 4 and the cladding tube 2 are welded by TIG welding or the like.
上記TIG溶接法により形成される溶接部５は、
第５図に示すように、端栓４の被覆管２の突合わ
せ部全周に沿つて設けられるが、この溶接部５の
欠陥は、安全性において問題となるのでＸ線透過
試験のような非破壊検査により、溶接部の健全性
を評価している。 The welded portion 5 formed by the above TIG welding method is
As shown in Fig. 5, the end plug 4 is provided along the entire circumference of the butt part of the cladding tube 2, but defects in this welded part 5 pose a safety problem, so The soundness of welds is evaluated using non-destructive testing.
上記溶接部の健全性の評価において、被覆管２
と端栓４との突合わせ面の溶接部５における溶込
不足領域１５（第６図）は、溶接品質上、溶接部
機械強度の低下をもたらして好ましくない。この
溶込不足領域１５は、被覆管２の端面と端栓４の
突合わせ面に位置し密着状態を保つているので、
この部分にＸ栓透過試験を行なつても、溶込不足
領域１５の空〓はわずかであり、Ｘ栓フイルムに
直接欠陥を検出することができない。 In the above-mentioned evaluation of the soundness of the welded part, cladding tube 2
The insufficient penetration region 15 (FIG. 6) in the welded portion 5 of the abutting surface of the end plug 4 and the end plug 4 is undesirable from the viewpoint of welding quality because it causes a decrease in the mechanical strength of the welded portion. This insufficient penetration region 15 is located at the abutting surface between the end surface of the cladding tube 2 and the end plug 4, and maintains a close contact state.
Even if an X plug permeation test is performed on this portion, the void in the insufficiently penetrated region 15 is so small that defects cannot be directly detected in the X plug film.
上記溶接部５が正常な溶接溶込みである場合に
は、第７図に示すように、端栓テーパ部の被覆管
２と端栓１０の空〓の一部に溶接金属１６が満た
されるため、Ｘ栓フイルム上空〓部の先端すなわ
ち溶接ノツチ先端が被覆管２と端栓４との突合わ
せ面から後退するので、間接的に第６図に示すよ
うな溶込み不良が存在しないことが判定される。 When the welded portion 5 has normal weld penetration, as shown in FIG. 7, part of the void between the cladding tube 2 and the end plug 10 in the tapered end plug portion is filled with the weld metal 16. Since the tip of the upper part of the X plug film, that is, the tip of the welding notch, recedes from the abutment surface of the cladding tube 2 and the end plug 4, it is indirectly determined that there is no penetration failure as shown in FIG. be done.
そこで第５図に示すように、端栓４の切頭錐形
部４ａと被覆管２との間の溶込幅Ｌが予め定めた
基準値以上の幅を有するかどうかをＸ線フイルム
上で目視判定により行なつている。上記溶込幅
L1は実測できないので、端栓４のベース面から
テーパギヤツプ部の先端までのノツチ長さL2を
測定し、溶込幅L1を求めるようにしている。 Therefore, as shown in FIG. 5, whether the penetration width L between the truncated conical portion 4a of the end plug 4 and the cladding tube 2 is greater than a predetermined reference value is checked on an X-ray film. This is done by visual judgment. Above penetration width
Since L1 cannot be measured, the notch length L2 from the base surface of the end plug 4 to the tip of the tapered gap portion is measured to determine the penetration width L1 .
しかし上記形式の原子炉核燃料棒では、端栓製
造公差やＸ線フイルム上でのL2寸法の読取り精
度等の問題があり、溶接部の健全性を正確に判定
しにくいという難点がある。 However, the reactor nuclear fuel rods of the above type have problems such as end plug manufacturing tolerances and the accuracy of reading the L2 dimension on X-ray film, making it difficult to accurately determine the soundness of the weld.
本発明は上記した点に鑑みてなされたもので、
端栓の被覆管への溶接不良を簡単に検出し、信頼
性のある原子炉核燃料棒を提供することを目的と
する。
The present invention has been made in view of the above points, and
The purpose of this invention is to easily detect defective welding of an end plug to a cladding tube and to provide a reliable nuclear fuel rod for a nuclear reactor.
本発明は、端栓の被覆管ねの嵌み込み部を、２
段のテーパ面とし１段目の嵌め込み部側テーパ部
を溶融させることでこのテーパ部における空〓の
有無をＸ栓透過試験等により確認することで溶接
溶込性判定を容易に行なうことで溶接不良を判別
できるようにした原子炉核燃料棒である。
In the present invention, the fitting portion of the cladding tube thread of the end plug is
By melting the tapered part on the side of the fitting part of the first stage and checking the presence or absence of voids in this tapered part by an X-plug transmission test, etc., welding penetration can be easily determined. This is a reactor nuclear fuel rod that can be identified as defective.
以下本発明の一実施例を図面につき説明する。 An embodiment of the present invention will be described below with reference to the drawings.
なお第１図において第５図と同一部材について
は同一符号を付す。 In FIG. 1, the same members as in FIG. 5 are given the same reference numerals.
第１図において符号１０は、被覆管２の両端部
に嵌合される端栓であつて、この端栓１０の切頭
円錐形をなす嵌め込み部１１は、２段のテーパ面
を有して構成されている。実施例における上記嵌
め込み部の２段のテーパ面は、基端部分のテーパ
面の角度を５度、先端部分のテーパ面の角度を20
度としている。 In FIG. 1, reference numeral 10 denotes an end plug that is fitted to both ends of the cladding tube 2, and the fitting portion 11 of the end plug 10, which is shaped like a truncated cone, has a two-step tapered surface. It is configured. In the two-step tapered surface of the above-mentioned fitting part in the embodiment, the angle of the tapered surface at the proximal end is 5 degrees, and the angle of the tapered surface at the distal end is 20 degrees.
I take it seriously.
すなわち上記嵌め込み部１１は、基端部分のテ
ーパ面１２の角度αが先端部分のテーパ面１３の
角度βより小さい角度に設定されている。上記テ
ーパ面１２の長さは、予め定めた基準値の溶込幅
L1に決められている。実施例における溶込幅L1
は0.5mmである。 That is, in the fitting portion 11, the angle α of the tapered surface 12 at the proximal end portion is set to be smaller than the angle β of the tapered surface 13 at the distal end portion. The length of the tapered surface 12 is the penetration width of a predetermined reference value.
It is set to L 1 . Penetration width L 1 in the example
is 0.5mm.
しかして端栓１０と被覆管２の突合わせ部を
TIG溶接法で溶接すると、突合わせ部に溶接部１
４が形成されることになる。 Therefore, the butt part of the end plug 10 and the cladding tube 2 is
When welding using the TIG welding method, there is a weld 1 at the butt part.
4 will be formed.
溶接部１４が、第２図に示すように、溶接溶込
性が正常な時には、嵌め込み部１１の１段目のテ
ーパ部分が溶接撹拌された状態にある。かかる状
態の溶接部１４をＸ線検査すると、Ｘ線イルム像
として１段目テーパ面１２の角度α部分すなわち
テーパ面の角度５度部分は検出されず、２段目テ
ーパ面１３の角度βすなわち角度20度の部分のみ
がノツチ状に表示され、基準値の溶込幅を有して
いることが判断されることになる。 As shown in FIG. 2, when the welding portion 14 has normal weld penetration, the first tapered portion of the fitting portion 11 is in a welded agitated state. When the welded part 14 in such a state is inspected by X-rays, the angle α portion of the first-stage tapered surface 12, that is, the 5-degree angle portion of the tapered surface, is not detected in the X-ray irradiation image, and the angle β of the second-stage tapered surface 13, that is, the 5-degree angle portion of the tapered surface is not detected. Only the 20 degree angle portion is displayed in a notch shape, and it is determined that the penetration width is the standard value.
一方溶接部１４が、第３図に示すように、溶接
溶込性が不十分な時には、被覆管２と端栓１０の
突合わせ面に融合不良が生じるとともに端栓１０
の１段目のテーパ部分が溶融しない状態にある。
かかる状態の溶接部１４をＸ線検査すると、Ｘ線
フイルム像として２段目テーパ面１３の角度βの
先端に連らなつて１段目テーパ面１２の空〓が鮮
明なくさび状ノツチとして表示される。すなわち
Ｘ線フイルムの１段目テーパ部分のノツチの有無
により溶接溶込不足が判定されることになる。 On the other hand, when the welded portion 14 has insufficient weld penetration as shown in FIG.
The first stage taper portion is not melted.
When the welded part 14 in such a state is subjected to an X-ray inspection, an X-ray film image shows that the void of the first-stage tapered surface 12 continues to the tip of the angle β of the second-stage tapered surface 13 as a clear wedge-shaped notch. be done. That is, insufficient weld penetration is determined based on the presence or absence of a notch in the first tapered portion of the X-ray film.
以上述べたように本発明によれば、溶接部の健
全性が合理的かつ容易に判定できるので、品質保
証上の管理が一層向上するという効果を奏する。
As described above, according to the present invention, the soundness of a welded portion can be determined rationally and easily, so that quality assurance management is further improved.
第１図は本発明による原子炉核燃料棒の要部を
示す断面図、第２図は端栓溶接部が正常状態であ
る場合を示す図、第３図は端栓溶接部が溶接不良
である場合を示す図、第４図は原子炉核燃料棒の
一部を省略して示す断面図、第５図は端栓溶接部
の従来の検査方法を示す図、第６図は従来の端栓
溶接部が溶接不良である場合を示す拡大図、第７
図は同端栓溶接部が正常である場合を示す拡大図
である。
２…被覆管、１０…端栓、１１…嵌め込み部、
１２，１３…テーパ面、１４…溶接部。
Figure 1 is a sectional view showing the main parts of the reactor nuclear fuel rod according to the present invention, Figure 2 is a diagram showing the end plug welded part in a normal state, and Figure 3 is the end plug welded part in a welding defect. Figure 4 is a cross-sectional view of a reactor nuclear fuel rod with some parts omitted; Figure 5 is a diagram showing a conventional inspection method for end plug welds; Figure 6 is a diagram showing conventional end plug welding. Enlarged view showing the case where the part is poorly welded, No. 7
The figure is an enlarged view showing a case where the same-end plug welded portion is normal. 2... Cladding tube, 10... End plug, 11... Fitting part,
12, 13...Tapered surface, 14...Welded part.
Claims (1)
の両端部に嵌合されかつ溶着される端栓とを有す
る原子炉核燃料棒において、端栓の被覆管との嵌
め込み部を、基端部分のテーパ面の角度を先端部
分のテーパ面の角度より小さい角度とした２段の
テーパ面とするとともに、基端部分のテーパ面の
長さを予め定めた溶込幅とし、１段目の嵌め込み
部側テーパ部を溶融させたことを特徴とする原子
炉核燃料棒。1. In a nuclear reactor nuclear fuel rod that has a cladding tube loaded with nuclear fuel material and an end plug that is fitted and welded to both ends of the cladding tube, the fitting part of the end plug with the cladding tube is connected to the base end portion. The angle of the tapered surface is smaller than the angle of the tapered surface at the distal end, making it a two-step tapered surface, and the length of the tapered surface at the proximal end is set to a predetermined penetration width, and the first step fitting part A reactor nuclear fuel rod characterized by having a fused side tapered part.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60063223A JPS61223580A (en) | 1985-03-29 | 1985-03-29 | Nuclear fuel rod for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60063223A JPS61223580A (en) | 1985-03-29 | 1985-03-29 | Nuclear fuel rod for nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61223580A JPS61223580A (en) | 1986-10-04 |
| JPH0220957B2 true JPH0220957B2 (en) | 1990-05-11 |
Family
ID=13222990
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60063223A Granted JPS61223580A (en) | 1985-03-29 | 1985-03-29 | Nuclear fuel rod for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61223580A (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5432149A (en) * | 1977-08-15 | 1979-03-09 | Westinghouse Electric Corp | Apparatus for welding edge plug to nuclear fuel rod |
| JPS5438489A (en) * | 1977-08-31 | 1979-03-23 | Toshiba Corp | Fuel rod |
-
1985
- 1985-03-29 JP JP60063223A patent/JPS61223580A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5432149A (en) * | 1977-08-15 | 1979-03-09 | Westinghouse Electric Corp | Apparatus for welding edge plug to nuclear fuel rod |
| JPS5438489A (en) * | 1977-08-31 | 1979-03-23 | Toshiba Corp | Fuel rod |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61223580A (en) | 1986-10-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US20020190099A1 (en) | Groove shape for single butt welding and inspection method of weld zone thereof | |
| US3183066A (en) | Article produced by metals joining and method for producing such articles | |
| JPH0220957B2 (en) | ||
| JP5126915B2 (en) | Manufacturing method of non-destructive welding specimens | |
| KR100834494B1 (en) | A method for tensile testing an end cap weld in a tube region of an elongated nuclear fuel element specimen having a weld and an apparatus for conducting a tensile test to initiate failure in an end cap weld in an elongated nuclear fuel element specimen having an axial dimension | |
| JP3249360B2 (en) | Inspection method of weld joint of welding rotor | |
| US6665363B1 (en) | Method of inspecting the welding of a sealed closure plug of a nuclear reactor fuel element | |
| JPH0447199B2 (en) | ||
| JP5491471B2 (en) | Analysis method of defect detection probability by ultrasonic testing | |
| JP2530011B2 (en) | How to repair a long housing | |
| JP2931667B2 (en) | How to seal fuel rods by welding | |
| JPH07130293A (en) | Non-destructive inspection method for welded member | |
| JP3199417B2 (en) | Standard specimen for non-destructive inspection of piping | |
| JP2006021214A (en) | Method for controlling welding quality of segment conductor | |
| US4631167A (en) | Method for the production of a nuclear reactor assembly and assembly obtained by this method | |
| JP3046926B2 (en) | Inspection method of fuel guide pin for reactor | |
| JPH0110633Y2 (en) | ||
| JPH0658413B2 (en) | Fuel rod and manufacturing method thereof | |
| JPH063469A (en) | Nuclear fuel element | |
| JP3247239B2 (en) | Prevention method of bend defect at toe of Uranami weld bead root with asymmetric throat thickness | |
| JP2000111328A (en) | Method for inspecting welding part of welding pipe | |
| KR101738012B1 (en) | Inspection method for cold fusion on fusion joint of polyethylene pipes | |
| JP2004219192A (en) | Seal welding structure of pipe and method for inspecting the same | |
| WO1988008970A1 (en) | Method of inspecting can seaming | |
| JPS63304156A (en) | Ultrasonic flaw detecting and inspecting device for steam turbine blade |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |