JPS6299432A - Fuel coated pipe comprising single zirconium base alloy - Google Patents
Fuel coated pipe comprising single zirconium base alloyInfo
- Publication number
- JPS6299432A JPS6299432A JP61248551A JP24855186A JPS6299432A JP S6299432 A JPS6299432 A JP S6299432A JP 61248551 A JP61248551 A JP 61248551A JP 24855186 A JP24855186 A JP 24855186A JP S6299432 A JPS6299432 A JP S6299432A
- Authority
- JP
- Japan
- Prior art keywords
- cladding
- fuel
- fuel cladding
- alloy
- base 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Metallurgy (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Physical Vapour Deposition (AREA)
- Chemically Coating (AREA)
- Rigid Pipes And Flexible Pipes (AREA)
- Powder Metallurgy (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Fuel-Injection Apparatus (AREA)
- Other Surface Treatments For Metallic Materials (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
発明の背景
この発明は加圧水形、沸騰水型のような軽水および重水
炉に適用される原子炉用のジルコニウム基合金からなる
燃料被覆に関する。この発明は特に、単一のジルコニウ
ムをベースにしだ材料からなる燃料被覆管に関する。BACKGROUND OF THE INVENTION This invention relates to a fuel cladding made of a zirconium-based alloy for use in nuclear reactors as applied to light water and heavy water reactors, such as pressurized water type and boiling water type reactors. The invention particularly relates to fuel cladding made of a single zirconium-based material.
従来、多数の該燃料被覆の設計例が提案されており、そ
れぞれＰＣＩ （ペレット−被覆−相互作用）による亀
裂の進展を最少にすることを目的としている。これらの
設計例はすべて、通常のジルコニウム基合金（たとえば
、ジルカロイ２捷たは４）管の内面に、薄肉内層として
比較的軟質の材料を配設することを包含している。A number of such fuel cladding designs have been proposed in the past, each aimed at minimizing the propagation of cracks due to PCI (pellet-cladding-interaction). All of these designs involve disposing a relatively soft material as a thin inner layer on the inner surface of a conventional zirconium-based alloy (eg, Zircaloy 2 or 4) tube.
軟質材料のコスト、およびそれを燃料被覆管内に具備さ
せるためのコストが燃料被覆管の最終コストに大きく付
加されることになる。耐ＰＣＩ性内張り材料は脚壁的に
は、完全に再結晶されたミクロ組織を有しており、通常
の被覆材料、ジルカロイ２および４に比較して、比較的
強度が低く、かつ水に対する耐食性が小さい。これらの
特性により、これを被覆管全体を形成する材料として利
用することは不適切になる。したがって、単一材料で燃
料被覆管を形成すると共に、優秀なＰＣＩ亀裂進展に対
する抵抗性、優秀な水に対する耐食性、および良好な構
造機械的性質を組合せて有する被覆を提供する燃料被覆
の設剖が必要になる。The cost of the soft material, and the cost of including it within the fuel cladding, adds significantly to the final cost of the fuel cladding. The PCI-resistant lining material has a fully recrystallized microstructure in the leg walls, which provides relatively low strength and water corrosion resistance compared to the usual cladding materials, Zircaloy 2 and 4. is small. These properties make it unsuitable for use as a material for forming entire cladding tubes. Therefore, a fuel cladding design that provides a combination of excellent PCI crack propagation resistance, excellent water corrosion resistance, and good structural mechanical properties while forming the fuel cladding in a single material is desirable. It becomes necessary.
発明の概要
この発明によれば、単一のジルコニウム基合金からなる
燃料被覆管が提供される。この被覆管は優秀な水に対す
る耐食性、および優秀なＰＣＩ亀裂進展に対する１１（
抗１′１：および良好な構造機械的性質を有する。した
がって、２層（軟質のＰＣ丁亀裂進展］１（抗性内層に
接合さ才する、強度および水に対する＋ｆｆ１１食性を
有する外層）からなる被覆管の心安性は除去される。こ
の発明の燃料被覆管は、冷間側７にして全体的に応力緩
和されたミクロ′Ｍ１織を有することが好捷しい。ミク
ロ組織中にはある程度の＋ｆｒ結晶等軸粒子が存在する
が、それはミクロ組織の１０体積％を越えるものではな
い。合理的な肉厚の被覆管に構造機械的性質をり、える
ために、観察できる再結晶粒子が存在１〜ないととが最
も好ましいことである。利用される合金は下記のジルコ
ニウム基合金の一つとすることができる：
表 １
１１ν１分 合 金 （重」１（
噌）Ａ Ｂ ＣＤ
ＥＩ−：ｎ ｏ、２−ｏ、６ ｏ、＋−ＪＱ
、６１．２〜１．７ ０．１５−知、６ ０．４−０．
６１＼Ｉｉ ＜ｏ、ｏａ ＜ｏ、ｏａ
Ｏ，０３−（］、０７］〔２
０＜６００ （６００＜６００ （６００（６
００総不純物〈１５ｏｏ４“＜１５００〈１５００〈１
５００〈１５０゜号：ｉ１′ｊ位はｐｐｍ。SUMMARY OF THE INVENTION According to the present invention, a fuel cladding tube made of a single zirconium-based alloy is provided. This cladding has excellent water corrosion resistance and excellent PCI crack propagation resistance.
Anti-1'1: and has good structural mechanical properties. Therefore, the safety of a cladding consisting of two layers (a soft PC crack propagation outer layer bonded to a resistant inner layer with strength and +ff11 erodibility against water) is eliminated.The fuel cladding of the present invention Preferably, the tube has an overall stress-relaxed micro'M1 weave on the cold side 7. Although there is some +fr crystal equiaxed grain in the microstructure, it is % by volume.In order to obtain structural and mechanical properties in a cladding of reasonable wall thickness, it is most preferred that there be no observable recrystallized particles. The alloy may be one of the following zirconium-based alloys: Table 1
噌）A B CD
EI-:no, 2-o, 6-o, +-JQ
, 61.2-1.7 0.15-chi, 6 0.4-0.
61\Ii <o, oa <o, oa
O,03-(],07][2 0<600 (600<600 (600(6
00 total impurities〈15oo4“＜1500〈1500〈1
500〈150゜No.: i1'j is ppm.
：総不純物には酸素が庁ｆれろ。: Oxygen should be included in the total impurities.
この発明の燃料被覆管は収縮ひずみ比が２捷たはそれ以
」−１好捷しくば２．５〜３．０、あるいはカーンズ（
Ｋｅａｒｎｓ） 半径ｆ値が少な（とも０．６５、そ
（−て好丑しくは少な（とも０．７により！＋！ｆ徴づ
けられる高度な異方性組織を有することが好ましい。The fuel cladding of the present invention has a shrinkage strain ratio of 2.5 to 3.0, or Kearns (2.5 to 3.0).
It is preferable to have a highly anisotropic structure characterized by a radius f value of small (both 0.65, - and preferably small (both 0.7!+!f).
表１に示される合金の酸素含量は４００ ｐｐｍ。The oxygen content of the alloy shown in Table 1 is 400 ppm.
より少ないことが好捷しい。総不純物量は、１０００
ｐｐｍ。より少ないことが好丑しい。Less is more. The total amount of impurities is 1000
ppm. Less is better.
この発明の前述ならびに他の特徴は、以下の詳細な説明
から明らかになるであろう。The foregoing as well as other features of the invention will become apparent from the detailed description below.
この発明において、ｔｌｌ−のジルコニウム基合金から
なる核燃料岐覆管が提供されている。選択される合金は
良好な水に対する耐食性、構造特性およびＰＣＩ抵抗性
を組合せた特性を有している。合金は表■に示されるも
のの一つから選択されることが好捷しい。また、この発
明においては前記被覆管のミクロ組織は冷間加工され、
かつ応力緩和されたもので、１０体体積上り少ない再結
晶粒子を含み、好ましくは観察可能な再結晶粒子を含量
ないという特徴を有するものが奸才しい。全体的に表１
に示される合金の一つから形成されると共に、前述の冷
間加工および応力除去ミクロ組織を有する燃料被覆管は
、水に対する耐食性、構造機械的性質およびＰＣＩ抵抗
性を組合せた特性を有しており、Ｐｗ′ＲおよびＢＷＲ
原子炉用の通常の燃料要素の設計に使用するのに適して
いると言うことができる。In this invention, a nuclear fuel manifold made of a tll-zirconium-based alloy is provided. The selected alloys have a combination of good water corrosion resistance, structural properties and PCI resistance. Preferably, the alloy is selected from one of those shown in Table 1. Further, in this invention, the microstructure of the cladding tube is cold worked,
Moreover, it is characterized by being stress-relaxed, containing less than 10 body volume recrystallized particles, and preferably containing no observable recrystallized particles. Overall Table 1
A fuel cladding formed from one of the alloys shown in Figure 1 and having the cold-worked and stress-relieving microstructure described above has properties that combine water corrosion resistance, structural mechanical properties, and PCI resistance. , Pw'R and BWR
It can be said that it is suitable for use in the design of conventional fuel elements for nuclear reactors.
合金Ｃ組成を有する燃料被覆は、応力除去捷たは部分的
もしくは完全再結晶状態の最終ミクロ組織を有している
。合金Ｃの実施例においてすず含有量が高いことにより
、表■に示される他の合金に比較してこの合金Ｃの構造
機械的性質が増強し、従って合金Ｃ材料からなる燃料被
覆を好ましい冷間加工および応力除去状態に加えて、部
分的および完全再結晶状態で使用することが可能になる
。合金Ｃ組成は表■に示される限界内に制御されること
が好捷しい。これらの合金成分限界は、酸素含有量が低
下されると共に、総不純物量も制御される点を除いて、
ジルカロイ−２およびジルカロイ−４からなる燃料被覆
の合金成分限界に対応するものである。A fuel cladding having an Alloy C composition has a final microstructure that is stress relieving, or partially or fully recrystallized. The high tin content in the Alloy C example enhances the structural mechanical properties of this Alloy C compared to the other alloys shown in Table 1, thus making fuel cladding made of Alloy C material preferred for cold forming. In addition to processing and stress relief conditions, it becomes possible to use it in partially and fully recrystallized conditions. Alloy C composition is preferably controlled within the limits shown in Table 3. These alloy composition limits are the same, except that the oxygen content is reduced and the total impurity content is also controlled.
This corresponds to the alloy composition limit for fuel cladding consisting of Zircaloy-2 and Zircaloy-4.
最も好ましくは、表［［に示される合金についての酸素
含有量が４００ ｐｐｍ、 より小さく、かつ総不純
物量（酸素を含む）が、１１０００ｐｐ、より小さいこ
とである。Most preferably, the oxygen content for the alloys shown in Table [[] is less than 400 ppm, and the total impurity amount (including oxygen) is less than 11000 ppm.
表 １１
Ｓｎ Ｌ２〜１７ Ｌ２〜１．
７Ｆｅ Ｏ，０７〜０．２０ ０
．１８〜０．２４Ｃｒ ０．０５〜０．ｊ
５ ｆｌ、０７〜０．１３Ｎｉ
Ｏ，０３〜０．０８ 不純物Ｑ
（６００１１１１ＴＩ （６
００）ｌｐＩｎ総不純物 （１５０Ｊ）ｐｍ （
＋５００ｐ＋−１ｍこの発明の燃料被覆のＰＣＩ抵抗性
は、最終焼な捷し管の結晶学的ホＩＩ織を制御して、収
縮ひずみ比２またはそれ以上、そして軽量しくは２．５
〜３゜０、あるいはカーンズ半径ｒ値が少な（とも０．
６５、そして好捷しくは少なくとも０．７であるように
することに、Ｌりさらに改善されると言うことができる
。Table 11 Sn L2-17 L2-1.
7FeO, 07~0.20 0
．． 18~0.24Cr 0.05~0. j
5fl, 07~0.13Ni
O,03~0.08 Impurity Q
(6001111TI (6
00)lpIn total impurities (150J)pm (
+500p+-1m The PCI resistance of the fuel cladding of this invention is controlled by the crystallographic F-II texture of the final annealed tube to achieve a shrinkage strain ratio of 2 or more and a light weight of 2.5.
~3°0, or the Kearns radius r value is small (both 0.
65, and preferably at least 0.7, it can be said that L is further improved.
上述の管を通常のジルカロイ−２およびジルカロイ−４
からなる燃料被覆の製造技術を用いて、当業者が容易に
製造できることは明らかであろう。さらに、この発明の
燃料被覆が、低い酸素含有量：（＜４５０ｐｐｍ）であ
ると共に、内径波面に接合された完全再結晶ジルコニウ
ム内張りを有するジルカロイ−２からなる燃料被覆にお
いて観察されるＩ）ＣＩ抵抗性と同様のＰＣＩ抵抗性を
示すと言うことができる。The above-mentioned tubes are made of ordinary Zircaloy-2 and Zircaloy-4.
It will be clear that one skilled in the art can easily manufacture a fuel cladding using the following techniques: Furthermore, the I) CI resistance observed in the fuel cladding of the present invention is composed of Zircaloy-2 with a low oxygen content: (<450 ppm) and a fully recrystallized zirconium lining bonded to the inner diameter corrugation. It can be said that it shows PCI resistance similar to that of
この発明の他の実施例はこの明細書の考察、捷たはここ
に開示された発明の実姉により当業者にとって明白で゛
あろう。ここでの明細および実施例は例示のだめのもの
であり、この発明の範囲は特許請求の範囲により限定さ
れるものである。Other embodiments of the invention will be apparent to those skilled in the art from consideration of this specification or the invention disclosed herein. The specification and examples herein are intended to be illustrative only, and the scope of the invention is limited by the scope of the claims.
Claims (1)
択された単一合金からなる燃料被覆管であつて、 前記被覆管の壁が完全に前記単一合金から形成され、且
つ前記壁が冷間加工され、かつ全体にわたつて応力除去
されたミクロ組織を有することを特徴とする燃料被覆管
。Claims: A fuel cladding made of a single alloy selected from the group of zirconium-based alloys A, B, C, D and E, wherein the wall of the cladding is formed entirely of the single alloy. A fuel cladding tube, characterized in that the wall is cold worked and has a stress-relieved microstructure throughout.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US79000585A | 1985-10-22 | 1985-10-22 | |
| US790005 | 1985-10-22 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6299432A true JPS6299432A (en) | 1987-05-08 |
Family
ID=25149366
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61248551A Pending JPS6299432A (en) | 1985-10-22 | 1986-10-21 | Fuel coated pipe comprising single zirconium base alloy |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JPS6299432A (en) |
| DE (1) | DE3635025A1 (en) |
| FR (1) | FR2588992B1 (en) |
| SE (1) | SE464267B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS63179034A (en) * | 1987-01-21 | 1988-07-23 | Kobe Steel Ltd | Corrosion-resisting zirconium alloy |
| JPH01147034A (en) * | 1987-10-22 | 1989-06-08 | Westinghouse Electric Corp <We> | Zirconium alloy for liner of fuel element of atomic reactor |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4778648A (en) * | 1987-04-24 | 1988-10-18 | Westinghouse Electric Corp. | Zirconium cladded pressurized water reactor nuclear fuel element |
| US6243433B1 (en) * | 1999-05-14 | 2001-06-05 | General Electic Co. | Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57134552A (en) * | 1981-02-13 | 1982-08-19 | Toshiba Corp | Zirconium alloy substrate |
| JPS5825466A (en) * | 1981-07-07 | 1983-02-15 | アクチ−ボラゲツト・アセア−アトム | Manufacture of zirconium base alloy-clad pipe |
| JPS58224139A (en) * | 1982-06-21 | 1983-12-26 | Hitachi Ltd | Zirconium alloy with high corrosion resistance |
| JPS59126763A (en) * | 1983-01-12 | 1984-07-21 | Hitachi Ltd | Production of zirconium alloy member |
| JPS6067648A (en) * | 1983-09-22 | 1985-04-18 | Hitachi Ltd | Nuclear fuel covering pipe and its preparation |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3804708A (en) * | 1971-11-24 | 1974-04-16 | United Nuclear Corp | Nuclear reactor fuel rod |
| US4770847A (en) * | 1982-06-01 | 1988-09-13 | General Electric Company | Control of differential growth in nuclear reactor components by control of metallurgical conditions |
| US4664881A (en) * | 1984-03-14 | 1987-05-12 | Westinghouse Electric Corp. | Zirconium base fuel cladding resistant to PCI crack propagation |
-
1986
- 1986-10-09 SE SE8604289A patent/SE464267B/en not_active IP Right Cessation
- 1986-10-15 DE DE19863635025 patent/DE3635025A1/en not_active Withdrawn
- 1986-10-21 JP JP61248551A patent/JPS6299432A/en active Pending
- 1986-10-22 FR FR868614651A patent/FR2588992B1/en not_active Expired - Lifetime
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57134552A (en) * | 1981-02-13 | 1982-08-19 | Toshiba Corp | Zirconium alloy substrate |
| JPS5825466A (en) * | 1981-07-07 | 1983-02-15 | アクチ−ボラゲツト・アセア−アトム | Manufacture of zirconium base alloy-clad pipe |
| JPS58224139A (en) * | 1982-06-21 | 1983-12-26 | Hitachi Ltd | Zirconium alloy with high corrosion resistance |
| JPS59126763A (en) * | 1983-01-12 | 1984-07-21 | Hitachi Ltd | Production of zirconium alloy member |
| JPS6067648A (en) * | 1983-09-22 | 1985-04-18 | Hitachi Ltd | Nuclear fuel covering pipe and its preparation |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS63179034A (en) * | 1987-01-21 | 1988-07-23 | Kobe Steel Ltd | Corrosion-resisting zirconium alloy |
| JPH01147034A (en) * | 1987-10-22 | 1989-06-08 | Westinghouse Electric Corp <We> | Zirconium alloy for liner of fuel element of atomic reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| SE8604289L (en) | 1987-04-23 |
| SE464267B (en) | 1991-03-25 |
| DE3635025A1 (en) | 1987-04-23 |
| FR2588992A1 (en) | 1987-04-24 |
| SE8604289D0 (en) | 1986-10-09 |
| FR2588992B1 (en) | 1990-08-17 |
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