JPH04148893A - Manufacture of zirconium alloy clad tube superior in mechanical strength and resistance against stress, corrosion and cracking - Google Patents
Manufacture of zirconium alloy clad tube superior in mechanical strength and resistance against stress, corrosion and crackingInfo
- Publication number
- JPH04148893A JPH04148893A JP2274622A JP27462290A JPH04148893A JP H04148893 A JPH04148893 A JP H04148893A JP 2274622 A JP2274622 A JP 2274622A JP 27462290 A JP27462290 A JP 27462290A JP H04148893 A JPH04148893 A JP H04148893A
- Authority
- JP
- Japan
- Prior art keywords
- alloy
- tube
- mechanical strength
- inner diameter
- zirconium alloy
- 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
- 229910001093 Zr alloy Inorganic materials 0.000 title claims abstract description 87
- 238000005260 corrosion Methods 0.000 title claims abstract description 21
- 230000007797 corrosion Effects 0.000 title claims abstract description 21
- 238000005336 cracking Methods 0.000 title claims abstract description 21
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 20
- 238000000034 method Methods 0.000 claims abstract description 27
- 238000000137 annealing Methods 0.000 claims description 19
- 238000005096 rolling process Methods 0.000 claims description 17
- 238000001953 recrystallisation Methods 0.000 claims description 15
- 238000005253 cladding Methods 0.000 claims description 12
- 238000012545 processing Methods 0.000 claims description 8
- 229910052751 metal Inorganic materials 0.000 abstract description 3
- 229910052726 zirconium Inorganic materials 0.000 abstract description 3
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 abstract description 2
- 239000002184 metal Substances 0.000 abstract description 2
- 229910045601 alloy Inorganic materials 0.000 description 11
- 239000000956 alloy Substances 0.000 description 11
- 239000003758 nuclear fuel Substances 0.000 description 9
- 239000013078 crystal Substances 0.000 description 7
- 239000008188 pellet Substances 0.000 description 4
- 239000007789 gas Substances 0.000 description 3
- 238000003754 machining Methods 0.000 description 3
- 238000010248 power generation Methods 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000000052 comparative effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000003993 interaction Effects 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000001125 extrusion Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
この発明は、優れた機械的強度および耐応力腐食割れ性
を示す原子炉燃料用ジルコニウム（以下、Ｚｒと記す）
合金被覆管の製造法に関するものである。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to zirconium (hereinafter referred to as Zr) for nuclear reactor fuel, which exhibits excellent mechanical strength and stress corrosion cracking resistance.
This invention relates to a method for manufacturing alloy clad tubes.
一般に、原子炉燃料の被覆管としてＺｒ合金被覆管が用
いられることはよく知られている。上記Ｚｒ合金被覆管
を製造するためのＺｒ合金は、ＪＩＳ規格のＨ４７５１
に規定されているジルカロイ２またはジルカロイ４が用
いられ、そのなかでも加圧水型原子炉の燃料用Ｚ「合金
被覆管としては特にジルカロイ４が用いられている。It is generally well known that Zr alloy cladding tubes are used as cladding tubes for nuclear reactor fuel. The Zr alloy for manufacturing the above Zr alloy clad tube is H4751 of JIS standard.
Zircaloy 2 or Zircaloy 4 as specified in the above is used, and among these, Zircaloy 4 is particularly used as the Z alloy clad tube for fuel of pressurized water reactors.
上記Ｚｒ合金被覆管は、押出し成形して得られた肉厚の
Ｚｒ合金素管をピルガ−圧延および再結晶焼鈍をそれぞ
れ１回または複数回繰返し施したのち、最終ピルガ−圧
延および歪取り焼鈍することにより製造され、」二記ピ
ルガー圧延は冷間圧延で行われ、上記再結晶焼鈍は真空
雰囲気中、温度５３０〜７６０°Ｃで行われ、最後の歪
取り焼鈍は４３０〜４９０°Ｃで行われる。The above Zr alloy clad tube is produced by subjecting a thick Zr alloy tube obtained by extrusion to repeated pilger rolling and recrystallization annealing one or more times, and then final pilger rolling and strain relief annealing. The above-mentioned recrystallization annealing is performed at a temperature of 530 to 760°C in a vacuum atmosphere, and the final strain relief annealing is performed at a temperature of 430 to 490°C. be exposed.
このようにして得られたＺｒ合金被覆管には、原子炉燃
料ペレットが充填され、原子炉燃料集合体に組立てられ
、炉心に挿入されて使用される〔これらの点については
、社団法人１日本金属学会編「改訂５版 金属便覧」平
成２年３月３１日。The Zr alloy cladding tube thus obtained is filled with reactor fuel pellets, assembled into a reactor fuel assembly, and inserted into the reactor core for use. “Revised 5th Edition Metals Handbook” edited by the Japan Institute of Metals, March 31, 1990.
丸善株式会社発行、８１２〜８１５参照〕。Published by Maruzen Co., Ltd., 812-815].
最近、電力供給源として原子力発電の比重が高まるにつ
れて原子力発電の高効率化が求められ、原子炉燃料集合
体の炉内滞在時間の長期化、原子炉燃料の高燃焼度化、
および原子炉の負荷追従運転等が実施され、それに伴っ
て、原子炉燃料ペレットとＺｒ合金被覆管との相互作用
による被覆管の応力腐食割れを起す可能性が高くなり、
長期にわたって続けて運転操業すると事故につながる恐
れがあるなとの問題が生してきた。Recently, as the importance of nuclear power generation as a power supply source has increased, higher efficiency of nuclear power generation has been required.
In addition, load following operation of the nuclear reactor is carried out, and as a result, the possibility of stress corrosion cracking of the cladding tube due to interaction between the reactor fuel pellet and the Zr alloy cladding tube increases.
The problem has arisen that continuous operation over a long period of time may lead to accidents.
そのため原子炉燃料ペレットとＺｒ合金被覆管との相互
作用による応力腐食割れを起すことのないＺｒ合金被覆
管を開発すべくいろいろな研究か成されており、例えば
、米国特許第４，７６５，１．７４号明細書には、Ｚｒ
合金素管をピルガ−圧延したのぢ再結晶焼鈍することに
よりＺｒ合金被覆管を製造する工程において、Ｚｒ合金
管の直径を５〜１２％拡管させたのち、約６７６．７℃
で再結晶焼鈍する工程を、上記ジルコニウム合金被覆管
を製造する工程の中間段階において少なくとも１回施す
ことにより耐応力１ｇ食割れ性に優れたＺｒ合金被覆管
を製造する方法が提案されてる。上記Ｚｒ合金管の直径
を拡管前の直径の５〜１２％拡管させたのち、約８７６
．７℃で再結晶焼鈍する工程を施すことによりＺｒ合金
管の稠密六方晶のＣ軸がＺｒ合金素管の半径方向に平行
に揃い、耐応力腐食割れ性が向上するとされている。Therefore, various studies have been conducted to develop Zr alloy cladding tubes that do not cause stress corrosion cracking due to the interaction between reactor fuel pellets and Zr alloy cladding tubes. .74 specification states that Zr
In the process of manufacturing a Zr alloy clad tube by recrystallization annealing after pilger rolling an alloy raw tube, the diameter of the Zr alloy tube is expanded by 5 to 12%, and then heated to approximately 676.7°C.
A method has been proposed for manufacturing a Zr alloy clad tube with excellent stress resistance of 1 g and corrosion cracking resistance by carrying out the step of recrystallization annealing at least once in the intermediate stage of the process of manufacturing the zirconium alloy clad tube. After expanding the diameter of the above Zr alloy tube by 5 to 12% of the diameter before expansion, it became approximately 876 mm.
．． It is said that by performing a recrystallization annealing process at 7° C., the C-axes of the dense hexagonal crystal of the Zr alloy tube are aligned parallel to the radial direction of the Zr alloy tube, improving stress corrosion cracking resistance.
ところが、稠密六方晶のＣ軸がＺｒ合金管の半径方向に
交差している方がＺｒ合金管の機械的強度は優れている
ために、上記Ｚ ｒ合金管の厚さ全体にわたって稠密六
方晶のＣ軸が半径方向に平行に揃ったＺ「合金管は、耐
応力腐食割れ性は向上するけれども機械的強度は従来よ
りも低下するという問題が生じてきた。However, since the mechanical strength of the Zr alloy tube is better when the C axis of the dense hexagonal crystal crosses the radial direction of the Zr alloy tube, the dense hexagonal crystal is Z-alloy tubes in which the C-axis is aligned parallel to the radial direction have improved stress corrosion cracking resistance, but a problem has arisen in that the mechanical strength is lower than before.
そこで応力腐食割れ性および機械的強度が共に優れたＺ
ｒ合金管を製造する研究がなされ、Ｚｒ合金素管を中間
ピルガ−圧延したのち再結晶焼鈍する工程では下記のＱ
値を２〜５に選んで内外径ともに同等割合いて軽減させ
、最終工程ではＱ値を中間ピルガ−圧延時よりも小さい
値に選ぶとともに内径よりも外径を大きい割合いて軽減
させる方法を採用し、第３図に示されるような、稠密六
方晶のＣ軸かＺｒ合金管内面部分では半径方向に平行に
揃うとともにＺｒ合金管外面部分てはＣ軸がＺｒ合金管
の半径方向に交差する集合組織を有するＺｒ合金被覆管
を製造する方法も提案されてる（特開平１．−３９０７
１１ｉ号公報参照）。Therefore, Z, which has excellent stress corrosion cracking resistance and mechanical strength,
Research has been conducted to manufacture r-alloy tubes, and the process of recrystallization annealing after intermediate pilger rolling of Zr-alloy tubes involves
By selecting a value between 2 and 5, both the inner and outer diameters are reduced by the same proportion, and in the final process, the Q value is selected to be a smaller value than during intermediate pilger rolling, and a method is adopted in which the outer diameter is reduced by a larger proportion than the inner diameter. , as shown in Fig. 3, the C axes of the dense hexagonal crystal are aligned parallel to the radial direction on the inner surface of the Zr alloy tube, and the C axes on the outer surface of the Zr alloy tube intersect with the radial direction of the Zr alloy tube. A method for manufacturing a Zr alloy cladding tube having a structure has also been proposed (Japanese Patent Application Laid-Open No. 1999-3907).
(See Publication No. 11i).
Ｑ−（（ｔ −ｔ） ／ｌ ） ／ ［ｔｄ。Q-((t-t)/l)/[td.
ただし、ｔｏ ：圧延前の管肉厚
ｔ ：圧延後の管肉厚
ｄ）／ｄｏ］
ｄｏ：圧延前の管平均径
ｄ ：圧延後の管平均径
〔発明が解決しようとする課題〕
しかし、」二記特開平１−３９０７１３号公報記載のＺ
ｒ合金被覆管の製造方法では、Ｚｒ合金管内面部分では
、稠密六方晶のＣ軸が半径方向に平行に揃い、同時にＺ
ｒ合金管外面部分ではＣ軸が半径方向に交差するような
組織を得ることは、ピルガ−圧延の制御方法が難しく、
困難であった。However, to: Pipe wall thickness before rolling t: Pipe wall thickness after rolling d)/do] do: Pipe average diameter before rolling d: Pipe average diameter after rolling [Problem to be solved by the invention] However, "2, Z described in Japanese Patent Application Laid-open No. 1-390713
In the method for manufacturing r-alloy clad tubes, in the inner surface of the Zr-alloy tube, the C axes of the close-packed hexagonal crystal are aligned parallel to the radial direction, and at the same time the Z
It is difficult to obtain a structure in which the C-axis intersects in the radial direction on the outer surface of the r-alloy tube using the pilger rolling control method.
It was difficult.
そこで、本発明者らは、かかる課題を解決すべく研究を
行った結果、
Ｚｒ合金素管を、外径を変化させずに内径を拡大させる
加工を施したのぢ再結晶焼鈍する工程を少なくとも１回
施すことにより機械的強度および耐応力腐食割れ性に優
れたＺｒ合金被覆管を得ることができるという知見を得
たのである。Therefore, the present inventors conducted research to solve this problem, and found that the Zr alloy tube was processed to enlarge the inner diameter without changing the outer diameter, and at least the process of recrystallization annealing was performed to enlarge the inner diameter without changing the outer diameter. They found that a Zr alloy clad tube with excellent mechanical strength and stress corrosion cracking resistance can be obtained by applying the method once.
この発明は、かかる知見に基づいて成されたものであっ
て、
Ｚｒ合金管をピルガ−圧延したのち再結晶焼鈍すること
によりＺｒ合金被覆管を製造する工程において、外径を
変化させずに内径を拡大させる加工を施したのち再結晶
焼鈍する工程を少なくとも１回施す機械的強度および耐
応力腐食割れ性に優れたＺｒ合金被覆管の製造法に特徴
を有するものである。This invention was made based on this knowledge, and in the process of manufacturing a Zr alloy clad tube by pilger rolling a Zr alloy tube and recrystallization annealing, the inner diameter can be changed without changing the outer diameter. This method is characterized by a method for manufacturing a Zr alloy cladding tube having excellent mechanical strength and stress corrosion cracking resistance, in which a step of recrystallization annealing is performed at least once after processing to enlarge the Zr alloy.
上記外径を変化させずに内径を拡大さぜる加工をＺｒ合
金管に施すと、Ｚｒ合金管の内面は最も加工率か大きく
、半径方向の歪も最大となるため、稠密六方晶のＣ軸か
Ｚｒ合金管の半径方向に揃った集合組織となり、耐応力
腐食割れ性が向上する。When a Zr alloy tube is subjected to the process of enlarging the inner diameter without changing the outer diameter, the inner surface of the Zr alloy tube has the highest processing rate and the largest strain in the radial direction, so the close-packed hexagonal C The texture becomes uniform in the radial direction of the Zr alloy tube, improving stress corrosion cracking resistance.
一方、Ｚｒ合金管の肉厚中央部および外面は加工率が小
さく、半径方向の歪も小さいため、稠密六方晶のＣ軸が
Ｚｒ合金管の半径方向に交差する集合組織となり、管全
体としての機械的強度が維持される。このようにして得
られたＺｒ合金被覆管は、内面か耐応力腐食割れ性に優
れかつ管全体としては機械的強度に優れたＺｒ合金被覆
管となり、機械的強度および耐応力腐食割れ性がともに
優れたＺｒ合金被覆管を製造することができるのである
。上記内面の耐応力腐食割れ性に優れたＺｒ合金被覆管
は、原子炉燃料ペレットを被覆するＺｒ合金被覆管とし
て十分に使用することができる。On the other hand, since the processing rate is small and the strain in the radial direction is small in the thick central part and outer surface of the Zr alloy tube, the C-axis of the close-packed hexagonal crystal forms a texture that intersects with the radial direction of the Zr alloy tube, and the tube as a whole becomes Mechanical strength is maintained. The thus obtained Zr alloy clad tube has excellent stress corrosion cracking resistance on the inner surface and excellent mechanical strength as a whole, and has both mechanical strength and stress corrosion cracking resistance. This makes it possible to manufacture excellent Zr alloy clad tubes. The Zr alloy clad tube with the above-mentioned inner surface having excellent stress corrosion cracking resistance can be satisfactorily used as a Zr alloy clad tube for coating nuclear reactor fuel pellets.
上記外径を変化させずに内径を拡大させる加工をＺｒ合
金管に施す時のＺｒ合金管の肉厚の減少率は、２〜１０
％か好ましい。その理由は、Ｚｒ合金管の肉厚の減少率
が２％未満では十分な加工率が得られず、】０％を越え
ると外面まで加工率が向上し、Ｚｒ合金管の肉厚全体に
亘って稠密六方晶のＣ軸が半径方向に揃った集合組織と
なるために、、Ｚｒ合金管の機械的強度が得られないこ
とによるものである。When the Zr alloy tube is subjected to the process of enlarging the inner diameter without changing the outer diameter, the reduction rate of the wall thickness of the Zr alloy tube is 2 to 10%.
% is preferable. The reason for this is that if the reduction rate of the wall thickness of the Zr alloy tube is less than 2%, a sufficient machining rate cannot be obtained, and if it exceeds 0%, the machining rate improves to the outer surface, and the machining rate increases over the entire wall thickness of the Zr alloy tube. This is because the mechanical strength of the Zr alloy tube cannot be obtained because the C-axis of the dense hexagonal crystal is aligned in the radial direction.
この発明の上記外径を変化させずに内径を拡大させる加
工を図面にもとづいて具体的に説明する。The process of enlarging the inner diameter without changing the outer diameter according to the present invention will be specifically explained based on the drawings.
第１図は、Ｚｒ合金素管にピルガ−圧延および再結晶焼
鈍を所定の回数繰返し施して得られたＺ「合金管を、外
径を変化させずに内径を拡大させる加工装置にセットし
た状態を示す断面概略図である。あらかじめＺｒ合金管
１の先端部をプラグ６か挿入できるように機械加工した
Ｚｒ合金管１を金型２に挿入し、先端部にプラグ６を挿
入したのち、引抜きロッド５をｍＭし、さらに、Ｚｒ合
金管］の先端部を中子４とチャック３で固定し、第１図
に示されるように、Ｚｒ合金管を加工装置にセットした
のち、第２図に示されるように引抜きロット５をＡ方向
に引張ると、Ｚｒ合金管の外径を変化させずに内径を拡
大させる加工を施すことができる。 この外径を変化さ
せずに内径を拡大させる加工は、Ｚｒ合金素管に１回ま
たは複数回施すことができる。また、Ｚｒ合金素管にピ
ルガ−圧延および再結晶焼鈍を所定の回数繰返し施す工
程と組合わせて適用してもよい。Figure 1 shows a Zr alloy tube obtained by repeatedly subjecting a Zr alloy tube to pilger rolling and recrystallization annealing a predetermined number of times, set in a processing device that enlarges the inner diameter without changing the outer diameter. 2 is a cross-sectional schematic diagram showing the Zr alloy tube 1. The Zr alloy tube 1, which has been machined in advance so that the tip of the Zr alloy tube 1 can be inserted with the plug 6, is inserted into the mold 2, and after inserting the plug 6 into the tip, it is pulled out. After fixing the tip of the Zr alloy tube with the core 4 and the chuck 3, and setting the Zr alloy tube in the processing equipment as shown in FIG. By pulling the drawn rod 5 in the direction A as shown, it is possible to expand the inner diameter of the Zr alloy tube without changing its outer diameter. , can be applied to the Zr alloy raw tube once or multiple times.Furthermore, it may be applied in combination with the process of repeatedly subjecting the Zr alloy raw tube to pilger rolling and recrystallization annealing a predetermined number of times.
つぎに、この発明を実施例に基づいて具体的に説明する
。Next, the present invention will be specifically explained based on examples.
外径：３．４インチ（ｌ１８．４ｍｍ） 、肉厚＝０．
Ｂインチ（１，５，２ｍｍ）の寸法を有し、
Ｓｎ：１．５重量％、 Ｆｅ：０．２重量％、Ｃｒ：
Ｏ，１重量％、
を含有し、残りがＺｒおよび不ｉ’ｉ丁避不純物からな
る組成のＺｒ合金押出し素管を用意した。Outer diameter: 3.4 inches (18.4 mm), wall thickness = 0.
It has dimensions of B inches (1, 5, 2 mm), Sn: 1.5% by weight, Fe: 0.2% by weight, Cr:
A Zr alloy extruded blank tube containing 1% by weight of O, with the remainder consisting of Zr and unavoidable impurities was prepared.
上記Ｚｒ合金押出し素管を、ピルガ−圧延したのち引続
いて真空雰囲気中、温度： ６８０’Ｃ５２時間保持の
条件で再結晶焼鈍する工程を３面繰返すことにより、
外径： １．２５インチ（３１，７５ｍｎ＋）、内径：
０．８５インチ（２１，５９龍）、の寸法を有するＺ
ｒ合金管を製造した。The above Zr alloy extruded raw tube was pilger rolled and then recrystallized annealed in a vacuum atmosphere at a temperature of 680'C for 52 hours by repeating the process on three sides to obtain an outer diameter of 1.25 inch ( 31,75mm+), inner diameter:
Z with dimensions of 0.85 inches (21,59 dragons)
An r-alloy tube was manufactured.
このＺｒ合金管に第１図および第２図に示されるような
外径を変化させずに内径を拡大させる加工を施し、第１
表に示される内径とし、内径増加率を計算して第１表に
示した。かかる内径増加率となるような外径を変化させ
ずに内径を拡大させる加工を施したＺ「合金管を、さら
に真空雰囲気中、温度二６８０℃、２時間保持の再結晶
焼鈍を施した。This Zr alloy tube was processed to enlarge the inner diameter without changing the outer diameter as shown in Figs.
The inner diameter was set as shown in the table, and the inner diameter increase rate was calculated and shown in Table 1. The Z"alloy tube, which had been processed to enlarge the inner diameter without changing the outer diameter so as to achieve such an inner diameter increase rate, was further subjected to recrystallization annealing at a temperature of 2,680° C. for 2 hours in a vacuum atmosphere.
上記加工および再結晶焼鈍を施したＺｒ合金管を、さら
にピルガ−圧延したのち引続いて真空雰囲気中、温度二
６８０℃、２時間保持の条件で再結晶焼鈍する工程を実
施したのち、最終ピルガ−圧延および真空雰囲気中、温
度＋４．７０’Ｃ１２時間保持の歪取り焼鈍することに
より、外径、０．３７４インチ（９，５ｍｍ） 、肉厚
： ０．００２インチ（０，５７ｍｍ）の・」′法を有
する実施例１〜３および比較例１〜２のＺｒ合金管を製
造した。The Zr alloy tube that has undergone the above processing and recrystallization annealing is further pilger rolled and then recrystallized in a vacuum atmosphere at a temperature of 2,680°C for 2 hours, after which the final pilger is rolled. - By rolling and strain relief annealing at +4.70'C for 12 hours in a vacuum atmosphere, the outer diameter is 0.374 inch (9.5 mm) and the wall thickness is 0.002 inch (0.57 mm). Zr alloy tubes of Examples 1 to 3 and Comparative Examples 1 to 2 using the '' method were manufactured.
これらＺｒ合金管を３６０℃に保持ｊ７、腐食性ガスと
してヨウ素ガスを濃度：Ｂ、Ｏｍｇ／ｃ♂となるように
充填し、さらにアルゴンガスにより内側がら応カニ ２
８．１ｋｇ／ｎｕｆｔで加圧した状態に保持し、破損に
至るまでの時間を測定する耐応力腐食割れ試験を実施し
、それらの測定結果をそれぞれ第１表に示した。These Zr alloy tubes were held at 360°C, filled with iodine gas as a corrosive gas to a concentration of B, Omg/c♂, and further heated from the inside with argon gas.
A stress corrosion cracking test was carried out in which the specimens were held under pressure at 8.1 kg/nuft and the time until failure was measured, and the measurement results are shown in Table 1.
さらにＺｒ合金管の機械的強度を評価するために、上記
Ｚｒ合金管に荷重をかけて押し潰し、ｚｒ合金管が偏重
化して亀裂が生じた時の高さ１１を測定し、
偏甲率−（ｈ。−ｈ）／ｈｏＸ１００％、〔但し、ｈａ
はＺｒ合金管の外径＋０．３７４インチ（９，５ｍｍ）
］を求め、それらの測定結果もそれぞれ第１表に示し
た。Furthermore, in order to evaluate the mechanical strength of the Zr alloy tube, the Zr alloy tube was crushed by applying a load, and the height 11 when the Zr alloy tube became unbalanced and cracked was measured, and the uneven shell ratio - (h.-h)/hoX100%, [however, ha
is the outer diameter of the Zr alloy tube + 0.374 inch (9.5 mm)
], and the measurement results are also shown in Table 1.
第１表に示される結果から、実施例１〜３の製造方法で
作製されたＺ「合金管は、機械的強度および耐応力腐食
割れ性が共に優れているに対し、この発明の条件から外
れた条件で作製された比較例１〜２のＺｒ合金管（第１
表において、この発明の条件から外れた条件には、※印
を付して示した。）に比べて、機械的強度または耐応力
腐食割れ性のうちいずれかが劣ることがわかる。From the results shown in Table 1, the Z alloy tubes produced by the manufacturing methods of Examples 1 to 3 have excellent mechanical strength and stress corrosion cracking resistance, but they do not meet the conditions of the present invention. Zr alloy tubes of Comparative Examples 1 and 2 manufactured under the same conditions (first
In the table, conditions that deviate from the conditions of this invention are marked with *. ) is inferior in either mechanical strength or stress corrosion cracking resistance.
」二連のように、この発明によると、最近の原子力発電
の効率化による原子炉燃料集合体の炉内滞在時間の長期
化、原子炉燃料の高燃焼度化、および原子炉の負荷追従
運転等に対して、応力腐食割れを起す恐れがなく、機械
的強度の優れたＺｒ合金被覆管を簡単な製造方法により
低コストで提供することかでき、原子炉の運転コストも
下げることができるなどの産業上優れた効果を奏するも
のである。'' According to this invention, the recent improvements in the efficiency of nuclear power generation have led to longer stay times of nuclear reactor fuel assemblies in the reactor, higher burnup of reactor fuel, and load-following operation of nuclear reactors. For example, Zr alloy cladding tubes with excellent mechanical strength and no risk of stress corrosion cracking can be provided at low cost using a simple manufacturing method, and the operating costs of nuclear reactors can also be lowered. It has excellent industrial effects.
第１図および第２図は、Ｚｒ合金素管にピルガ−圧延お
よび再結晶焼鈍を所定の回数繰返し施して得られたＺｒ
合金管を、外径を変化させずに内径を拡大させる加工装
置にセットした状態を示す断面概略図、
第３図は、稠密大方品のＣ軸かＺｒ合金管内面部分では
半径方向に平行に揃うとともにＺｒ合金管外面部分では
Ｃ軸がＺｒ合金管の半径方向に交差する集合組織を有す
るＺｒ合金被覆管の説明図である。
１：Ｚｒ合金管 ２：金 型
３：チヤツク ４：中 子
５：引抜きロッド ６：プラグFigures 1 and 2 show Zr alloy tubes obtained by repeatedly subjecting Zr alloy tubes to pilger rolling and recrystallization annealing a predetermined number of times.
Figure 3 is a schematic cross-sectional view showing the alloy tube set in a processing device that enlarges the inner diameter without changing the outer diameter. FIG. 2 is an explanatory diagram of a Zr alloy clad tube having a texture in which the C axes are aligned and intersect with the radial direction of the Zr alloy tube in the outer surface portion of the Zr alloy tube. 1: Zr alloy tube 2: Mold 3: Chuck 4: Core 5: Pulling rod 6: Plug
Claims (2)
晶焼鈍をそれぞれ１回または複数回繰返し施したのち、
最終ピルガー圧延および歪取り焼鈍することによりジル
コニウム合金被覆管を製造する工程において、 ジルコニウム合金管の外径を変化させずに内径を拡大さ
せる加工を施す工程を少なくとも１回施すことを特徴と
する機械的強度および耐応力腐食割れ性に優れたジルコ
ニウム合金被覆管の製造法。(1) After repeatedly subjecting the zirconium alloy tube to Pilger rolling and recrystallization annealing once or multiple times,
A machine characterized in that, in the process of manufacturing a zirconium alloy clad tube by final pilger rolling and strain relief annealing, the process of enlarging the inner diameter of the zirconium alloy tube without changing its outer diameter is carried out at least once. A method for producing zirconium alloy cladding with excellent mechanical strength and stress corrosion cracking resistance.
施すことによる内径の増加率は、２〜１０％であること
を特徴とする請求項１記載の機械的強度および耐応力腐
食割れ性に優れたジルコニウム合金被覆管の製造法。(2) Mechanical strength and stress corrosion cracking resistance according to claim 1, characterized in that the increase rate of the inner diameter by performing processing to enlarge the inner diameter without changing the outer diameter is 2 to 10%. A method for manufacturing zirconium alloy cladding with excellent properties.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2274622A JPH04148893A (en) | 1990-10-12 | 1990-10-12 | Manufacture of zirconium alloy clad tube superior in mechanical strength and resistance against stress, corrosion and cracking |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2274622A JPH04148893A (en) | 1990-10-12 | 1990-10-12 | Manufacture of zirconium alloy clad tube superior in mechanical strength and resistance against stress, corrosion and cracking |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH04148893A true JPH04148893A (en) | 1992-05-21 |
Family
ID=17544289
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2274622A Pending JPH04148893A (en) | 1990-10-12 | 1990-10-12 | Manufacture of zirconium alloy clad tube superior in mechanical strength and resistance against stress, corrosion and cracking |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH04148893A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009018347A (en) * | 1997-02-12 | 2009-01-29 | Cie Europeenne Du Zirconium-Cezus | Method for manufacturing guide tube of nuclear reactor fuel assembly, mandrel for forming guide tube and guide tube obtained |
-
1990
- 1990-10-12 JP JP2274622A patent/JPH04148893A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009018347A (en) * | 1997-02-12 | 2009-01-29 | Cie Europeenne Du Zirconium-Cezus | Method for manufacturing guide tube of nuclear reactor fuel assembly, mandrel for forming guide tube and guide tube obtained |
| JP2012058258A (en) * | 1997-02-12 | 2012-03-22 | Cie Europeenne Du Zirconium-Cezus | Method for manufacturing guide tube of nuclear reactor fuel assembly, mandrel for forming guide tube and guide tube obtained |
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