JPH0499255A - Production of zirconium alloy clad tube having superior resistance to stress corrosion cracking - Google Patents
Production of zirconium alloy clad tube having superior resistance to stress corrosion crackingInfo
- Publication number
- JPH0499255A JPH0499255A JP2212641A JP21264190A JPH0499255A JP H0499255 A JPH0499255 A JP H0499255A JP 2212641 A JP2212641 A JP 2212641A JP 21264190 A JP21264190 A JP 21264190A JP H0499255 A JPH0499255 A JP H0499255A
- Authority
- JP
- Japan
- Prior art keywords
- tube
- pilger rolling
- corrosion cracking
- stress corrosion
- recrystallization annealing
- 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 26
- 238000005260 corrosion Methods 0.000 title claims abstract description 15
- 230000007797 corrosion Effects 0.000 title claims abstract description 15
- 238000005336 cracking Methods 0.000 title claims abstract description 15
- 238000004519 manufacturing process Methods 0.000 title claims description 15
- 238000000137 annealing Methods 0.000 claims abstract description 27
- 238000005096 rolling process Methods 0.000 claims abstract description 24
- 238000001953 recrystallisation Methods 0.000 claims abstract description 18
- 238000005253 cladding Methods 0.000 claims description 11
- 238000000034 method Methods 0.000 claims description 5
- 238000012545 processing Methods 0.000 claims description 5
- 229910045601 alloy Inorganic materials 0.000 description 7
- 239000000956 alloy Substances 0.000 description 7
- 230000000052 comparative effect Effects 0.000 description 7
- 239000003758 nuclear fuel Substances 0.000 description 7
- 239000007789 gas Substances 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
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000008188 pellet Substances 0.000 description 2
- 229910052726 zirconium Inorganic materials 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-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
- 238000005097 cold rolling Methods 0.000 description 1
- 230000000694 effects Effects 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
- 230000003993 interaction Effects 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000011160 research Methods 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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B21—MECHANICAL METAL-WORKING WITHOUT ESSENTIALLY REMOVING MATERIAL; PUNCHING METAL
- B21B—ROLLING OF METAL
- B21B21/00—Pilgrim-step tube-rolling, i.e. pilger mills
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B21—MECHANICAL METAL-WORKING WITHOUT ESSENTIALLY REMOVING MATERIAL; PUNCHING METAL
- B21B—ROLLING OF METAL
- B21B3/00—Rolling materials of special alloys so far as the composition of the alloy requires or permits special rolling methods or sequences ; Rolling of aluminium, copper, zinc or other non-ferrous metals
-
- 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
- Metal Extraction Processes (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
この発明は、原子炉燃料の被覆管として用いた場合に、
優れた耐応力腐食割れ性を示すジルコニウム（以下、Ｚ
ｒで示す。）合金被覆管の製造法に関するものである。[Detailed Description of the Invention] [Industrial Field of Application] When used as a cladding tube for nuclear reactor fuel, the present invention provides
Zirconium (hereinafter referred to as Z) exhibits excellent stress corrosion cracking resistance.
Indicated by r. ) 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Ｚｒ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 defined in the above is used, and among these, Zircaloy 4 is particularly used as a Zr alloy cladding tube for fuel of a pressurized water reactor.
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、上記ピル
ガ−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℃で行われ、最後の歪取り
焼鈍は４３０〜４９０℃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 pilger rolling is performed by cold rolling, the recrystallization annealing is performed in a vacuum atmosphere at a temperature of 530 to 760°C, and the final strain relief annealing is performed at a temperature of 430 to 490°C.
二のようにして得られたＺ「合金被覆管には、原子炉燃
料ベレットが充填され、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 Z alloy cladding tube obtained as described in step 2 is filled with reactor fuel pellets, assembled into a reactor fuel assembly, and inserted into the reactor core for use. 1 Edited by the Japan Institute of Metals, “Revised 5th Edition Metals Handbook” March 31, 1990.
丸善株式会社発行、８１２〜８１５参照〕。Published by Maruzen Co., Ltd., 812-815].
しかし、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
くなるなどの課題があった。However, recently, as the importance of nuclear power generation as a power supply source has increased, there has been a demand for higher efficiency in nuclear power generation. Load follow-up operation of the reactor was carried out, and as a result, there were problems such as an increased possibility of stress corrosion cracking of the cladding tube due to interaction between the reactor fuel pellets and the Zr alloy cladding tube.
そこで、本発明者らは、かかる課題を解決し、従来より
もさらに耐応力腐食割れ性に優れたＺｒ合金被覆管を製
造すべく研究を行った結果、上記ピルガ−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すＺ「合金被
覆管の製造工程において、上記ピルガ−圧延に続いて外
径減少率：１〜ｌ５９６の引張り加工を施したのち再結
晶焼鈍する工程を少なくとも１回含むことにより従来よ
りもさらに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 manufacture a Zr alloy clad tube with even better stress corrosion cracking resistance than conventional ones. By including at least one step of recrystallization annealing after performing tensile processing with an outer diameter reduction rate of 1 to 1596 following the above-mentioned pilger rolling in the Z "alloy clad tube manufacturing process that is repeated once or multiple times. It was discovered that it is possible to obtain a Zr alloy clad tube with even better stress corrosion cracking resistance than conventional ones.
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合金素管に、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Ｚｒ合金被覆管を
製造する工程において、上記ピルガ−圧延に続いて外径
減少率：１〜１５％の引張り加工を施したのち再結晶焼
鈍する工程を少なくとも１回含む、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。The present invention was made based on this knowledge, and after subjecting a Zr alloy raw tube to repeated pilger rolling and recrystallization annealing one or more times, the final pilger
In the process of manufacturing a Zr alloy cladding tube by rolling and strain relief annealing, the process of performing recrystallization annealing after performing tensile processing with an outer diameter reduction rate of 1 to 15% following the pilger rolling is performed at least once. The present invention is characterized by a method for manufacturing a Zr alloy clad tube with excellent stress corrosion cracking resistance.
この発明の耐応力腐食割れ性に優れたＺｒ合金被覆管の
製造法において、上記引張り加工による外径減少率を１
〜１５％に限定した理由は、外径減少率が１％未満では
耐応力腐食割れ性向上に効果がなく、一方、外径減少率
が１５％を越えると局部変形を起こすので好ましくない
ことによるものである。In the method of manufacturing a Zr alloy cladding tube with excellent stress corrosion cracking resistance according to the present invention, the outer diameter reduction rate due to the above-mentioned tensile processing is reduced to 1.
The reason why it is limited to ~15% is that if the outer diameter reduction rate is less than 1%, it will not be effective in improving stress corrosion cracking resistance, whereas if the outer diameter reduction rate exceeds 15%, local deformation will occur, which is undesirable. It is something.
つぎに、この発明を、実施例にもと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（８６，４關）、肉厚１０９６イン
チ（１５，２＋ａｍ）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および不可避不純物からなる組成
のＺｒ合金押出し素管を用意した。It has dimensions of outer diameter = 3.4 inches (86.4 inches), wall thickness 1096 inches (15.2 + am), Sn: 1.5 weight%, Fe: 0.2 weight%, Cr:
An extruded Zr alloy tube containing 1% by weight of O and the remainder consisting of Zr and unavoidable impurities was prepared.
実施例１〜４および比較例１〜２
上記押出し素管を第１ピルガ−圧延し、続いて第１表に
示される外径減少率となるように引張り加工したのち、
真空雰囲気中で第１再結晶焼鈍を施し、ついで、第２ピ
ルガ−圧延および真空雰囲気中で第２再結晶焼鈍、並び
に第３ピルガ−圧延および真空雰囲気中で第３再結晶焼
鈍を施したのち、最終ピルガ−圧延および真空雰囲気中
で歪取り焼鈍を施すことにより外径：０．３７４インチ
（９，５關）、肉厚：０．０２２インチ（（１，５７ｍ
ｍ）の寸法を有する実施例１〜４および比較例１〜２の
Ｚｒ合金被覆管を製造した。Examples 1 to 4 and Comparative Examples 1 to 2 The above-mentioned extruded raw pipe was first pilger rolled, and then tensile processed to achieve the outer diameter reduction rate shown in Table 1.
After performing a first recrystallization annealing in a vacuum atmosphere, then a second pilger rolling and a second recrystallization annealing in a vacuum atmosphere, and a third pilger rolling and a third recrystallization annealing in a vacuum atmosphere. , by final pilger rolling and strain relief annealing in a vacuum atmosphere, the outer diameter: 0.374 inch (9.5 mm), wall thickness: 0.022 inch ((1,57 m)
Zr alloy clad tubes of Examples 1 to 4 and Comparative Examples 1 to 2 having dimensions of m) were manufactured.
実施例５〜８および比較例３〜４
上記押出し素管を第１ピルガ−圧延したのち、真空雰囲
気中で第１再結晶焼鈍して外径、２．５インチ（６３，
５ｍｍ） 、肉厚： ０．４３インチ（１０，９關）の
寸法を有する中間素管を製造し、この中間素管を第２ピ
ルガ−圧延し、続いて第２表に示される外径減少率とな
るように引張り加工したのち、真空雰囲気中で第２再結
晶焼鈍し、さらに第３ピルガ−圧延および真空雰囲気中
で第３再結晶焼鈍を施したのち、最終ピルガ−圧延およ
び真空雰囲気中で歪取り焼鈍することにより外径＋［１
，３７４インチ（９，５ｍｍ）、肉厚：（１，０２２イ
ンチ（０，５７ｉｍ）の寸法を有する実施例５〜８およ
び比較例３〜４のＺｒ合金被覆管を製造した。Examples 5 to 8 and Comparative Examples 3 to 4 After first pilger rolling the above-mentioned extruded raw tube, the first recrystallization annealing was performed in a vacuum atmosphere to give an outer diameter of 2.5 inches (63,
5 mm), wall thickness: 0.43 inch (10.9 mm), this intermediate blank tube was subjected to a second pilger rolling, and then the outer diameter was reduced as shown in Table 2. After tensile processing to obtain the desired ratio, a second recrystallization annealing is performed in a vacuum atmosphere, a third pilger rolling and a third recrystallization annealing in a vacuum atmosphere, and a final pilger rolling and a vacuum atmosphere. By performing strain relief annealing at
, 374 inches (9.5 mm), wall thickness: (1,022 inches (0.57 mm)) Zr alloy clad tubes of Examples 5 to 8 and Comparative Examples 3 to 4 were manufactured.
従来例
上記押出し素管を、先ず第１ピルガ−圧延したのち真空
雰囲気中の第１再結晶焼鈍を施し、さらにピルガ−圧延
および真空雰囲気中で再結晶焼鈍をそれぞれ２回づつ施
したのち、最終ピルガ−圧延および真空雰囲気中で歪取
り焼鈍することにより、外径＋０．３７４インチ（９，
５ｍｍ） 、肉厚：０．０２２インチ（０，５７ｍｍ）
の寸法を有する従来例のＺｒ合金被覆管を製造した。Conventional Example The above extruded raw tube is first pilger rolled, then subjected to first recrystallization annealing in a vacuum atmosphere, and then subjected to pilger rolling and recrystallization annealing twice in a vacuum atmosphere, and then final By pilger rolling and strain relief annealing in a vacuum atmosphere, the outer diameter is +0.374 inch (9,
5mm), wall thickness: 0.022 inch (0.57mm)
A conventional Zr alloy cladding tube having dimensions of .
上記実施例１〜８、比較例１〜４および従来例の製造工
程を第１表に示す。第１表に示された上記実施例１〜８
、比較例１〜４および従来例の製造方法で作製されたＺ
ｒ合金被覆管を３６０℃に保持し、腐食性ガスとしてヨ
ウ素ガスを濃度二６．０ｇ ／ ｃｄとなるように充填
し、さらにアルゴンガスにより内側から応カニ ２８．
１ｋｉ／−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。Table 1 shows the manufacturing processes of Examples 1 to 8, Comparative Examples 1 to 4, and the conventional example. Examples 1 to 8 above as shown in Table 1
, Z produced by the manufacturing method of Comparative Examples 1 to 4 and conventional example
The r-alloy clad tube was maintained at 360°C, filled with iodine gas as a corrosive gas to a concentration of 26.0 g/cd, and further oxidized from the inside with argon gas. 28.
A stress corrosion cracking test was carried out in which the specimens were kept under pressure of 1 ki/- and the time until failure was measured, and the measurement results are shown in Table 1.
第１表に示される結果から、実施例１〜８の製造方法で
作製されたＺ「合金被覆管は、いずれも従来例の製造方
法で作製されたＺ「合金被覆管と比べて、耐応力腐食割
れ性が優れており、またこの発明の条件から外れた条件
で行われる比較例１〜４の製造方法で製造されたＺｒ合
金被覆管（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。）は、耐応力腐食割れ
性が劣ることがわかる。From the results shown in Table 1, it can be seen that the Z-alloy clad tubes manufactured by the manufacturing methods of Examples 1 to 8 have higher stress resistance than the Z-alloy clad tubes manufactured by the conventional manufacturing method. Zr alloy clad tubes manufactured by the manufacturing methods of Comparative Examples 1 to 4, which have excellent corrosion cracking resistance and are conducted under conditions outside the conditions of this invention (in Table 1, It can be seen that the specimens (marked with *) have poor stress corrosion cracking resistance.
上述のように、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可能性が少なく、長
期にわたって続けて運転操業できることができるＺ「合
金被覆管を提供することができる。As described above, the present invention is applicable to the recent improvements in the efficiency of nuclear power generation, such as the lengthening of the stay time of nuclear reactor fuel assemblies in the reactor, the increase in burnup of reactor fuel, and the load following operation of nuclear reactors. On the other hand, it is possible to provide a Z-alloy clad pipe that is less likely to cause stress corrosion cracking and can be operated continuously for a long period of time.
Claims (1)
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、 上記ピルガー圧延に続いて外径減少率：１〜１５％の引
張り加工を施したのち再結晶焼鈍する工程を少なくとも
１回含む ことを特徴とする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) In the process of manufacturing a zirconium alloy clad tube by repeatedly subjecting a zirconium alloy tube to Pilger rolling and recrystallization annealing once or multiple times, and then subjecting it to final Pilger rolling and strain relief annealing, the above-mentioned Pilger rolling A method for producing a zirconium alloy cladding tube having excellent stress corrosion cracking resistance, comprising the steps of: followed by tensile processing with an outer diameter reduction rate of 1 to 15%, and recrystallization annealing at least once.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2212641A JPH0499255A (en) | 1990-08-10 | 1990-08-10 | Production of zirconium alloy clad tube having superior resistance to stress corrosion cracking |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2212641A JPH0499255A (en) | 1990-08-10 | 1990-08-10 | Production of zirconium alloy clad tube having superior resistance to stress corrosion cracking |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0499255A true JPH0499255A (en) | 1992-03-31 |
Family
ID=16626007
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2212641A Pending JPH0499255A (en) | 1990-08-10 | 1990-08-10 | Production of zirconium alloy clad tube having superior resistance to stress corrosion cracking |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0499255A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8257518B2 (en) | 2003-01-08 | 2012-09-04 | Westinghouse Electric Sweden Ab | Method, use and device relating to nuclear light water reactors |
-
1990
- 1990-08-10 JP JP2212641A patent/JPH0499255A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8257518B2 (en) | 2003-01-08 | 2012-09-04 | Westinghouse Electric Sweden Ab | Method, use and device relating to nuclear light water reactors |
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