JP3371303B2 - Reactor fuel cladding - Google Patents
Reactor fuel claddingInfo
- Publication number
- JP3371303B2 JP3371303B2 JP07787894A JP7787894A JP3371303B2 JP 3371303 B2 JP3371303 B2 JP 3371303B2 JP 07787894 A JP07787894 A JP 07787894A JP 7787894 A JP7787894 A JP 7787894A JP 3371303 B2 JP3371303 B2 JP 3371303B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- rolling
- less
- lining layer
- zirconium
- 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 - Fee Related
Links
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
-
- 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
- Pressure Welding/Diffusion-Bonding (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子炉用燃料棒に用い
られる原子炉用燃料被覆管に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor fuel cladding tube used in a nuclear reactor fuel rod.
【０００２】[0002]
【従来の技術】軽水又は重水冷却型原子炉用燃料集合体
には通常ジルコニウム合金からなる燃料被覆管が用いら
れている。ジルコニウム合金製被覆管は中性子の照射を
受けると照射脆化し、応力腐蝕割れによる破損が起きや
すくなる。応力腐蝕割れ（ＳＣＣ，Stress Corrosion C
racking ）を防止するために、被覆管内面に純度の高い
ジルコニウムを内張りすることが知られている。2. Description of the Related Art A fuel cladding tube made of a zirconium alloy is usually used for a fuel assembly for a light water or heavy water cooling type nuclear reactor. When a zirconium alloy cladding tube is irradiated with neutrons, it becomes embrittled by irradiation and is easily damaged by stress corrosion cracking. Stress corrosion cracking (SCC, Stress Corrosion C
In order to prevent racking), it is known to line the inside of the cladding tube with high-purity zirconium.
【０００３】即ち、図２は燃料棒の縦断面の構成を示す
説明図である。図３は図２の横断面の構成を示す説明図
である。図に示す通り、軽水又は重水冷却型原子炉用燃
料棒には、通常ジルコニウム合金からなる燃料被覆管２
が用いられ、内部に多数の燃料ペレット１とプレナムス
プリング３とが装填され、上下部端栓４で密封して燃料
棒とされる。That is, FIG. 2 is an explanatory view showing the structure of a vertical cross section of a fuel rod. FIG. 3 is an explanatory diagram showing the configuration of the cross section of FIG. As shown in the figure, the fuel rod for a light water or heavy water cooled reactor is usually a fuel cladding tube 2 made of a zirconium alloy.
Is used, a large number of fuel pellets 1 and a plenum spring 3 are loaded inside, and sealed with upper and lower end plugs 4 to form a fuel rod.
【０００４】ところで、ジルコニウム合金製の燃料被覆
管は中性子の照射を受けると照射脆化し、応力腐蝕割れ
による破損が起き易くなる。そこで、図３に示すよう
に、応力腐蝕割れを防止するために、燃料被覆管２内面
にジルカロイ合金に比べて軟質な純度の高いジルコニウ
ム層５を内張りすることが知られている。By the way, a fuel cladding tube made of a zirconium alloy is irradiated with neutrons to be embrittled by irradiation, and is likely to be damaged by stress corrosion cracking. Therefore, as shown in FIG. 3, in order to prevent stress corrosion cracking, it is known to line the inner surface of the fuel cladding tube 2 with a zirconium layer 5, which is softer and has a higher purity than a zircaloy alloy.
【０００５】米国特許第 4,300,492号によれば、純ジル
コニウムの不純物含有量の合計は 1000ppm以上 5000ppm
以下であり、そのうち酸素含有量は1200ppm 以下であ
る。このようなジルコニウムは所謂「商用の原子炉級ジ
ルコニウムスポンジ」であり、その他の不純物量は表１
に示す通りである。尚、燃料被覆管は外径８〜20mm、肉
厚 0.4〜1.5 mmで上述の内張り厚は0.03〜0.2 mmであ
る。According to US Pat. No. 4,300,492, the total impurity content of pure zirconium is not less than 1000 ppm and not more than 5000 ppm.
The oxygen content is 1200 ppm or less. Such zirconium is a so-called "commercial reactor-grade zirconium sponge", and the amount of other impurities is shown in Table 1.
As shown in. The fuel cladding has an outer diameter of 8 to 20 mm, a wall thickness of 0.4 to 1.5 mm, and the above-mentioned lining thickness of 0.03 to 0.2 mm.
【０００６】[0006]
【表１】 [Table 1]
【０００７】ところで、このような燃料被覆管では、被
覆管の製造欠陥や異物とのフレッティングにより、リー
クを起し、被覆管内に水が侵入すると内面のジルコニウ
ム層が急激に酸化し、燃料の破損が拡大し、燃料棒内の
放射能が多量に原子炉炉水中に放出されるおそれがあっ
た。By the way, in such a fuel cladding tube, a leak occurs due to manufacturing defects of the cladding tube and fretting with foreign matter, and when water enters the cladding tube, the zirconium layer on the inner surface is rapidly oxidized and the fuel There was a risk that the damage would spread and a large amount of radioactivity in the fuel rods would be released into the reactor water.
【０００８】また、このような燃料の破損拡大を防止す
るためには内面の純ジルコニウムに鉄等を添加すること
が考えられ、このような元素成分を増やすことによって
内張りの急激な酸化は抑制されることが予測される。Further, in order to prevent such fuel damage expansion, it is considered that iron or the like is added to pure zirconium on the inner surface. By increasing such elemental components, rapid oxidation of the inner lining is suppressed. Is expected to occur.
【０００９】[0009]
【発明が解決しようとする課題】しかしながら、ジルコ
ニウム層として、純ジルコニウムに鉄等を添加した場合
には、応力腐蝕割れに対する耐性は相対的に低下する新
たな欠点が生じることとなる。However, when iron or the like is added to pure zirconium as the zirconium layer, a new defect occurs in which the resistance to stress corrosion cracking relatively decreases.
【００１０】本発明では、応力腐蝕割れに対する耐性を
損なうことなく、このような破損の拡大の防止を可能と
する信頼性の高い燃料集合体を提供するものであり、内
面の急激な酸化に対する抑制力を維持しつつ、応力腐蝕
割れに対する耐性を向上させた信頼性の高い原子炉用燃
料被覆管を提供するものである。The present invention provides a highly reliable fuel assembly capable of preventing the expansion of such damage without impairing the resistance to stress corrosion cracking, and suppresses the rapid oxidation of the inner surface. Provided is a highly reliable fuel cladding tube for a nuclear reactor, which has improved resistance to stress corrosion cracking while maintaining force.
【００１１】[0011]
【課題を解決するための手段】本請求項１に記載の発明
に係る原子炉用燃料被覆管では、内部に核燃料を収納す
るジルコニウム合金製原子炉用燃料被覆管基材と、前記
燃料被覆管基材の内側に前記ジルコニウム合金と冶金的
に結合したジルコニウム製の内張り層とを有した燃料被
覆管において、前記内張り層が、０．２％以上１％以下
の微量の鉄と、酸素を１２００ｐｐｍ以下と、その他不
可避不純物の合計が２０００ｐｐｍ以下の成分である高
純度ジルコニウムからなり、前記ジルコニウム合金と前
記内張り層とを冶金的に結合させるための圧延・焼き鈍
し工程において、１−圧延後断面積／圧延前断面積で定
義される被覆管加工率を０．８以上にして圧延する最終
圧延工程と該最終圧延工程の後の最終焼き鈍し工程とを
経ることにより前記内張り層の結晶粒径が１０μｍ以下
にされているものである。A fuel cladding tube for a nuclear reactor according to the present invention is a zirconium alloy fuel cladding tube base material for containing a nuclear fuel therein, and the fuel cladding tube. In a fuel cladding tube having a zirconium lining layer metallurgically bonded to the zirconium alloy inside a substrate, the lining layer is 0.2% or more and 1% or less.
Trace amount of iron and oxygen less than 1200ppm, and other
The total amount of inevitable impurities is less than 2000ppm
In a rolling / annealing step for metallurgically bonding the zirconium alloy and the lining layer, which is made of pure zirconium, and is determined by 1-cross-sectional area after rolling / cross-sectional area before rolling.
The grain size of the lining layer is set to 10 μm or less by going through a final rolling step of rolling with a cladding tube working rate of 0.8 or more, which is defined as the above, and a final annealing step after the final rolling step. Is.
【００１２】また、本請求項２に記載の発明に係る原子
炉用燃料被覆管では、内部に核燃料を収納するジルコニ
ウム合金製原子炉用燃料被覆管基材と、前記燃料被覆管
基材の内側に前記ジルコニウム合金と冶金的に結合した
ジルコニウム製の内張り層とを有した燃料被覆管におい
て、前記内張り層が、０．２％以上１％以下の微量の鉄
と、酸素を６００ｐｐｍ以下と、その他不可避不純物の
合計が１０００ｐｐｍ以下の成分である高純度ジルコニ
ウムからなり、前記ジルコニウム合金と前記内張り層と
を冶金的に結合させるための圧延・焼き鈍し工程におい
て、１−圧延後断面積／圧延前断面積で定義される被覆
管加工率を０．８以上にして圧延する最終圧延工程と該
最終圧延工程の後の焼き鈍し温度約５７０℃及び焼き鈍
し時間約２時間の最終焼き鈍し工程とを経ることにより
前記内張り層の結晶粒径が７μｍ以下にされているもの
である。Further, in the fuel cladding for a nuclear reactor according to the present invention, a zirconium alloy fuel cladding for a nuclear reactor containing a nuclear fuel therein, and an inside of the fuel cladding for the reactor. A fuel cladding tube having a zirconium lining layer metallurgically bonded to the zirconium alloy, wherein the lining layer is a trace amount of iron of 0.2% to 1%.
And oxygen below 600ppm, and other unavoidable impurities
High-purity zirconium containing 1000 ppm or less in total
In a rolling / annealing step for metallurgically bonding the zirconium alloy and the lining layer, the coating being defined by 1-rolled cross-sectional area / pre-rolled cross-sectional area
By going through a final rolling step of rolling with a pipe working rate of 0.8 or more and a final annealing step of an annealing temperature of about 570 ° C. and an annealing time of about 2 hours after the final rolling step.
The crystal grain size of the lining layer is 7 μm or less.
【００１３】[0013]
【作用】本発明においては、内部に核燃料を収納するジ
ルコニウム合金製原子炉用燃料被覆管基材の内側に冶金
的に結合したジルコニウム製の内張り層が、０．２％以
上１％以下の微量の鉄と、酸素を１２００ｐｐｍ以下
と、その他不可避不純物の合計が２０００ｐｐｍ以下の
成分である高純度ジルコニウムからなり；前記内張り層
の結晶粒径が、１０μｍ以下であるものであるため、急
激な酸化に対する耐性を向上させ、応力腐蝕割れに対す
る耐性が低下しない。According to the present invention, the zirconium lining layer metallurgically bonded to the inside of the zirconium alloy fuel clad base material for a nuclear reactor containing the nuclear fuel is 0.2% or more.
1% or less of trace iron and 1200ppm or less of oxygen
And the total of other unavoidable impurities is 2000ppm or less
It consists of high-purity zirconium as a component; since the crystal grain size of the lining layer is 10 μm or less, resistance to rapid oxidation is improved and resistance to stress corrosion cracking does not decrease.
【００１４】即ち、燃料被覆管の酸化による破損拡大を
防止するためには内面のジルコニウム製内張り層を構成
する純ジルコニウムに微量の鉄を 0.2％以上１％以下添
加することによって内面のジルコニウム層の急激な酸化
は抑制される。しかしながら、これら微量の鉄を添加し
た場合には、応力腐蝕割れに対する耐性が相対的に低下
する。That is, in order to prevent the damage from spreading due to oxidation of the fuel cladding tube, a trace amount of iron is added to pure zirconium constituting the inner surface zirconium lining layer in an amount of 0.2% or more and 1% or less so that the zirconium layer in the inner surface is Rapid oxidation is suppressed. However, when these trace amounts of iron are added, the resistance to stress corrosion cracking relatively decreases.
【００１５】従って、本発明では、この高純度ジルコニ
ウム内張り層の結晶粒径を１０μｍ以下とすることによ
って応力腐蝕割れ性の耐性が向上する。また、より好ま
しくは７μｍ以下とすることによって、応力腐蝕割れ性
の耐性が更に向上する。Therefore, in the present invention, the resistance to stress corrosion cracking is improved by setting the crystal grain size of the high-purity zirconium lining layer to 10 μm or less. Further, more preferably by setting it to 7 μm or less, the resistance to stress corrosion cracking is further improved.
【００１６】また、ジルコニウム製内張り層は、高純度
ジルコニウム中に微量の鉄を０．２％以上１％以下含む
素材を準備し、前記冶金的に結合させる圧延・焼き鈍し
工程のうち、圧延時の被覆管加工率（即ち、１−圧延後
断面積／圧延前断面積）が０．８以上の最終圧延工程
と、該最終圧延工程の後の最終焼き鈍し工程を行うこと
により高純度ジルコニウム内張り層の結晶粒径を１０μ
ｍ以下とすることができ、更に、最終焼き鈍し工程で、
焼き鈍し温度を約５７０℃、焼き鈍し時間を約２時間行
うことによって高純度ジルコニウム内張り層の結晶粒径
を７μｍ以下とすることができる。The zirconium lining layer is prepared by preparing a material containing a trace amount of iron in high-purity zirconium in an amount of 0.2% or more and 1% or less and performing metallurgically bonding in the rolling / annealing step. By performing a final rolling step having a cladding processing rate (that is, 1-cross-sectional area after rolling / cross-sectional area before rolling) of 0.8 or more and a final annealing step after the final rolling step, a high-purity zirconium lining layer is obtained. Crystal grain size is 10μ
m or less, and in the final annealing step,
By performing the annealing temperature at about 570 ° C. and the annealing time for about 2 hours, the crystal grain size of the high-purity zirconium lining layer can be set to 7 μm or less.
【００１７】更に、内張り層に鉄又は鉄とニッケルを添
加すると急激な酸化に対する耐性が向上するが、好まし
くは内張り層が、微量の鉄を 0.2％以上１％以下含んで
なるものでは、耐性が飛躍的（例えば 100倍以上）に向
上することが確認された。Further, when iron or iron and nickel are added to the lining layer, the resistance to rapid oxidation is improved. However, when the lining layer contains a trace amount of iron of 0.2% or more and 1% or less, the resistance is low. It was confirmed that it could be dramatically improved (for example, 100 times or more).
【００１８】また、内張り層が、酸素の含有量が1200pp
m 以下、より好ましくは 600ppm 以下であるもの、ま
た、その他不純物の合計が2000ppm 以下、より好ましく
は1000ppm 以下であるものでは、応力腐蝕割れに対する
耐性が劣化しない。これは、機械的性質の「伸び」が変
化するため等の理由が考えられるが、詳しいことは不明
である。The lining layer has an oxygen content of 1200 pp.
If it is m or less, more preferably 600 ppm or less, and the total of other impurities is 2000 ppm or less, more preferably 1000 ppm or less, the resistance to stress corrosion cracking does not deteriorate. This may be because the "elongation" of mechanical properties changes, but the details are unknown.
【００１９】以上、個々に詳説したように、内部に核燃
料を収納するジルコニウム合金製原子炉用燃料被覆管基
材と、前記被覆管基材の内側に前記ジルコニウム合金と
冶金的に結合したジルコニウム製の内張り層とを有した
燃料被覆管において、前記内張り層が、０．２％以上１
％以下の微量の鉄と、酸素を６００ｐｐｍ以下と、その
他不可避不純物の合計が１０００ｐｐｍ以下の成分であ
る高純度ジルコニウムからなり、前記内張り層の結晶粒
径が、７μｍ以下であるものであるため、応力腐蝕割れ
に対する耐性を損なうことなく、破損の拡大の防止を可
能とする信頼性の高い燃料集合体を得ることができる。As described in detail above, a fuel cladding tube base material for a nuclear reactor made of a zirconium alloy which contains a nuclear fuel therein, and a zirconium alloy metallurgically bonded to the zirconium alloy inside the cladding tube base material. In the fuel cladding tube having an inner lining layer of 0.2% or more, 1
% Trace iron and oxygen less than 600ppm,
The total amount of other unavoidable impurities is 1000ppm or less.
That consists of high purity zirconium, crystal grain size of the lining layer, since they are at 7μm or less, without compromising resistance to stress corrosion cracking, high fuel assembly reliability that is capable of preventing expansion of damage You can get the body.
【００２０】[0020]
【実施例】図１は本発明の原子炉用燃料被覆管の一実施
例の製造を示す工程図である。即ち、図２及び図３に示
した構成の内張り付き被覆管を製作するに当たって、被
覆管の内面に内張りするジルコニウムに鉄を添加して、
図１に示す製造工程により内張り付き被覆管を製作し、
耐食性及び耐ＳＣＣ性を検討した。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1 is a process diagram showing the manufacture of an embodiment of a fuel cladding tube for a nuclear reactor of the present invention. That is, in manufacturing the cladding tube with the lining having the structure shown in FIGS. 2 and 3, iron is added to zirconium lining the inner surface of the cladding tube,
The cladding tube with the lining is manufactured by the manufacturing process shown in FIG.
The corrosion resistance and SCC resistance were examined.
【００２１】本実施例においては、内張り層の鉄の含有
量を０．５％、最終圧延時の被覆管加工率（即ち、１−
圧延後断面積／圧延前断面積）を０．８以上、最終焼き
鈍し温度を約５７０℃、最終焼き鈍し時間を約２時間と
して、高純度ジルコニウム内張り層の結晶粒径が７μｍ
以下とした被覆管を得た。In this example, the iron content of the lining layer was 0.5%, and the cladding pipe working ratio at the final rolling (that is, 1-
The cross-sectional area after rolling / the cross-sectional area before rolling) is 0.8 or more, the final annealing temperature is about 570 ° C., and the final annealing time is about 2 hours, and the crystal grain size of the high-purity zirconium lining layer is 7 μm.
The following coated tube was obtained.
【００２２】得られた燃料被覆管の化学成分を従来の被
覆管の化学成分と比較したものを次の表２に示す。表２
について、比較例１は内張りなしの被覆管で、従来のジ
ルコニウム合金であるジルカロイ２のものである。尚、
比較例２と本実施例の被覆管基体部は、比較例１と同じ
ものを用い、表２には内張り部のみの化学成分を示し
た。また、比較例２の数値は、従来の純ジルコニウムの
ものである。Table 2 below shows a comparison of the chemical composition of the obtained fuel cladding tube with that of a conventional cladding tube. Table 2
Comparative Example 1 is a cladding tube without an inner lining and is made of Zircaloy 2 which is a conventional zirconium alloy. still,
As the cladding tube base portion of Comparative Example 2 and this Example, the same one as in Comparative Example 1 was used, and Table 2 shows the chemical components only in the lining portion. Moreover, the numerical value of the comparative example 2 is that of the conventional pure zirconium.
【００２３】[0023]
【表２】 [Table 2]
【００２４】更に、本実施例の被覆管と従来被覆管の内
面の耐食性試験及びＳＣＣ試験結果を表３に示す。この
耐食性試験は 400℃の高温水蒸気中で７２時間の試験を
行った結果であり、腐蝕増量の数値が小さいほど酸化が
進みにくく耐食性がよいことを意味する。また、ＳＣＣ
試験はヨウ素雰囲気中（ヨウ素濃度１×１０-5ｇ／ｃｍ
3 ）における内圧印加によるＳＣＣ試験を実施したもの
であり、伸びの値が大きいほど軟らかく耐応力腐蝕割れ
特性（耐ＳＣＣ性）が優れていることを意味する。Further, Table 3 shows the results of the corrosion resistance test and SCC test of the inner surface of the cladding tube of this example and the conventional cladding tube. This corrosion resistance test is the result of conducting a test for 72 hours in high temperature steam at 400 ° C., and a smaller value of the amount of corrosion increase means that the oxidation is less likely to proceed and the corrosion resistance is better. Also, SCC
The test was carried out in an iodine atmosphere (iodine concentration 1 × 10 −5 g / cm
The SCC test was conducted by applying an internal pressure in 3 ), and the larger the elongation value, the softer the stress corrosion cracking resistance (SCC resistance).
【００２５】[0025]
【表３】 [Table 3]
【００２６】表２に示す通り、本発明による実施例で
は、鉄の組成が比較例１及び２と比べて約０．５％増や
していることが判る。また、表３に示す通り、本発明に
よる内張り付き被覆管では、耐食性は比較例１と同様に
良好で、比較例２に比較して著しく優れており、しか
も、耐応力腐蝕割れ性（耐ＳＣＣ性）が比較例２と同様
に優れていることが判る。As shown in Table 2, it can be seen that in the examples according to the present invention, the composition of iron is increased by about 0.5% as compared with Comparative examples 1 and 2. Further, as shown in Table 3, in the cladding tube with the inner lining according to the present invention, the corrosion resistance was as good as that of Comparative Example 1, and was significantly superior to that of Comparative Example 2, and moreover, the stress corrosion cracking resistance (SCC resistance) It can be seen that the property) is as excellent as that of Comparative Example 2.
【００２７】従って、鉄の添加によって、内面のジルコ
ニウム層の急激な酸化は抑制される。一方、鉄の添加に
よって生じる応力腐蝕割れに対する耐性の低下は、添加
された鉄の結晶粒径が７μｍであることにより、応力腐
蝕割れ性の耐性が向上する。Therefore, the rapid oxidation of the zirconium layer on the inner surface is suppressed by the addition of iron. On the other hand, with respect to the decrease in resistance to stress corrosion cracking caused by the addition of iron, the resistance to stress corrosion cracking is improved because the crystal grain size of added iron is 7 μm.
【００２８】以上のように、本発明によれば、被覆管内
張りの耐食性を向上させる一方、耐応力腐蝕割れ性能を
保持させることができ、応力腐蝕割れに対する耐性が高
く、且つ、万が一の破損に対しても、内面が急激に酸化
して破損が拡大することのない、健全性の高い燃料被覆
管を得ることができる。As described above, according to the present invention, while the corrosion resistance of the cladding lining can be improved, the stress corrosion cracking resistance can be maintained, the resistance to stress corrosion cracking is high, and in the unlikely event of damage. On the other hand, it is possible to obtain a highly sound fuel clad tube in which the inner surface is not rapidly oxidized and the damage is not expanded.
【００２９】尚、以上の実施例の製造条件は所定の結晶
粒径を得る上で無数の組み合わせがあり、同業者であれ
ば、試作試験を繰返すことにより適当な加工度と焼き鈍
し条件の組み合わせを選ぶことが可能である。The manufacturing conditions of the above examples have innumerable combinations for obtaining a predetermined crystal grain size, and those skilled in the art can repeat a trial test to obtain an appropriate combination of working degree and annealing conditions. It is possible to choose.
【００３０】[0030]
【発明の効果】本発明は以上説明したとおり、応力腐蝕
割れに対する耐性を損なうことなく、破損の拡大の防止
を可能とする信頼性の高い燃料集合体を提供するもので
あり、内面の急激な酸化に対する抑制力を維持しつつ、
応力腐蝕割れに対する耐性を向上させた信頼性の高い原
子炉用燃料被覆管を得ることができるという効果があ
る。As described above, the present invention provides a highly reliable fuel assembly capable of preventing the spread of damage without impairing the resistance to stress corrosion cracking, and has a sharp inner surface. While maintaining the ability to suppress oxidation,
There is an effect that it is possible to obtain a highly reliable fuel cladding tube for a nuclear reactor with improved resistance to stress corrosion cracking.
【図１】本発明の原子炉用燃料被覆管の一実施例の製造
を示す工程図である。FIG. 1 is a process chart showing the production of an embodiment of a fuel cladding tube for a nuclear reactor of the present invention.
【図２】図２は燃料棒の縦断面の構成を示す説明図であ
る。FIG. 2 is an explanatory diagram showing a configuration of a vertical cross section of a fuel rod.
【図３】図２の横断面の構成を示す説明図である。FIG. 3 is an explanatory diagram showing a configuration of a cross section of FIG.
１…燃料ペレット、 ２…燃料被覆管、 ３…プレナムスプリング、 ４…上下部端栓、 ５…ジルコニウム層、 1 ... Fuel pellets, 2 ... Fuel cladding, 3 ... Plenum spring, 4 ... Upper and lower end plugs, 5 ... zirconium layer,
Claims (2)
金製原子炉用燃料被覆管基材と、前記燃料被覆管基材の
内側に前記ジルコニウム合金と冶金的に結合したジルコ
ニウム製の内張り層とを有した燃料被覆管において、 前記内張り層が、０．２％以上１％以下の微量の鉄と、
酸素を１２００ｐｐｍ以下と、その他不可避不純物の合
計が２０００ｐｐｍ以下の成分である高純度ジルコニウ
ムからなり、 前記ジルコニウム合金と前記内張り層とを冶金的に結合
させるための圧延・焼き鈍し工程において、１−圧延後
断面積／圧延前断面積で定義される被覆管加工率を０．
８以上にして圧延する最終圧延工程と該最終圧延工程の
後の最終焼き鈍し工程とを経ることにより前記内張り層
の結晶粒径が１０μｍ以下にされていることを特徴とす
る原子炉用燃料被覆管。1. A zirconium alloy containing a nuclear fuel therein.
A fuel clad tube base material for a nuclear reactor made of gold, and the fuel clad tube base material
Zirco metallurgically bonded to the zirconium alloy inside
In a fuel cladding tube having a lining layer made of nickel, The lining layer isA trace amount of iron of 0.2% or more and 1% or less,
If oxygen is less than 1200ppm and other unavoidable impurities
High-purity zirconium with a total content of 2000ppm or less
It consists of Metallurgically bonding the zirconium alloy and the lining layer
In the rolling / annealing process to1-after rolling
The cladding tube processing rate defined by the cross-sectional area / pre-rolling cross-sectional area is 0.
8 or moreThe final rolling step of rolling and the final rolling step
By going through the final annealing step laterSaid lining layer
Is characterized by having a crystal grain size of 10 μm or less
Fuel cladding for nuclear reactors.
金製原子炉用燃料被覆管基材と、前記燃料被覆管基材の
内側に前記ジルコニウム合金と冶金的に結合したジルコ
ニウム製の内張り層とを有した燃料被覆管において、 前記内張り層が、０．２％以上１％以下の微量の鉄と、
酸素を６００ｐｐｍ以下と、その他不可避不純物の合計
が１０００ｐｐｍ以下の成分である高純度ジルコニウム
からなり、 前記ジルコニウム合金と前記内張り層とを冶金的に結合
させるための圧延・焼き鈍し工程において、１−圧延後
断面積／圧延前断面積で定義される被覆管加工率を０．
８以上にして圧延する最終圧延工程と該最終圧延工程の
後の焼き鈍し温度約５７０℃及び焼き鈍し時間約２時間
の最終焼き鈍し工程とを経ることにより前記内張り層の
結晶粒径が７μｍ以下にされていることを特徴とする原
子炉用燃料被覆管。2. A zirconium alloy containing a nuclear fuel therein.
A fuel clad tube base material for a nuclear reactor made of gold, and the fuel clad tube base material
Zirco metallurgically bonded to the zirconium alloy inside
In a fuel cladding tube having a lining layer made of nickel, The lining layer isA trace amount of iron of 0.2% or more and 1% or less,
Oxygen 600ppm or less and the total of other unavoidable impurities
High-purity zirconium whose content is 1000ppm or less
Consists of Metallurgically bonding the zirconium alloy and the lining layer
In the rolling / annealing process to1-after rolling
The cladding tube processing rate defined by the cross-sectional area / pre-rolling cross-sectional area is 0.
8 or moreThe final rolling step of rolling and the final rolling step
Subsequent annealing temperature of about 570 ° C and annealing time of about 2 hours
By going through the final annealing process ofSaid lining layerof
Raw material characterized by having a crystal grain size of 7 μm or less
Fuel cladding for child reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07787894A JP3371303B2 (en) | 1994-03-25 | 1994-03-25 | Reactor fuel cladding |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07787894A JP3371303B2 (en) | 1994-03-25 | 1994-03-25 | Reactor fuel cladding |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH07260971A JPH07260971A (en) | 1995-10-13 |
| JP3371303B2 true JP3371303B2 (en) | 2003-01-27 |
Family
ID=13646330
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP07787894A Expired - Fee Related JP3371303B2 (en) | 1994-03-25 | 1994-03-25 | Reactor fuel cladding |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3371303B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4879842B2 (en) * | 2007-08-20 | 2012-02-22 | Ｊｘ日鉱日石金属株式会社 | Zirconium crucible |
-
1994
- 1994-03-25 JP JP07787894A patent/JP3371303B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH07260971A (en) | 1995-10-13 |
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