JPS62188744A - Corrosion resistant hafnium alloy - Google Patents
Corrosion resistant hafnium alloyInfo
- Publication number
- JPS62188744A JPS62188744A JP3154286A JP3154286A JPS62188744A JP S62188744 A JPS62188744 A JP S62188744A JP 3154286 A JP3154286 A JP 3154286A JP 3154286 A JP3154286 A JP 3154286A JP S62188744 A JPS62188744 A JP S62188744A
- Authority
- JP
- Japan
- Prior art keywords
- alloy
- corrosion resistance
- water
- corrosion resistant
- hafnium 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
- 230000007797 corrosion Effects 0.000 title claims abstract description 19
- 238000005260 corrosion Methods 0.000 title claims abstract description 19
- 229910001029 Hf alloy Inorganic materials 0.000 title claims abstract description 13
- 239000000203 mixture Substances 0.000 claims 1
- 239000000126 substance Substances 0.000 claims 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 11
- 239000000463 material Substances 0.000 abstract description 9
- 229910045601 alloy Inorganic materials 0.000 abstract description 6
- 239000000956 alloy Substances 0.000 abstract description 6
- 238000004519 manufacturing process Methods 0.000 abstract description 2
- 230000002542 deteriorative effect Effects 0.000 abstract 1
- 238000010521 absorption reaction Methods 0.000 description 4
- 229910052580 B4C Inorganic materials 0.000 description 3
- 230000006866 deterioration Effects 0.000 description 2
- 229910052735 hafnium Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 230000000052 comparative effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000011017 operating method Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C27/00—Alloys based on rhenium or a refractory metal not mentioned in groups C22C14/00 or C22C16/00
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は、高温高圧の水若しくは水蒸気に対する耐食性
に優れた軽水炉制御材料に関する。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a light water reactor control material that has excellent corrosion resistance against high-temperature, high-pressure water or steam.
（従来の技術とその問題点）
軽水冷却型原子炉の制御材料は、核分裂反応に必要な熱
中性子を吸収して原子炉の出力を制御するものであり、
・熱中性子吸収特性
・高温高圧の水、水蒸気に対する耐食性が要求される。(Conventional technology and its problems) Control materials for light water-cooled nuclear reactors control the output of the reactor by absorbing the thermal neutrons necessary for the nuclear fission reaction. Corrosion resistance against water and steam is required.
現在、軽水冷却型原子炉用制御材料としては、ボロンカ
ーバイド（８４Ｃ）やＡｇ−１５％ Ｉｎ−５％ Ｃｄ
合金などが使用されている。これらのうち、後者は経済
的理由から漸減する方向にあり、前者が主流となってい
る。Ｂ４Ｃは、ステンレテ管中にパウダー状又はペレッ
ト状で詰められて制御材料として使用されており、その
平均寿命は４〜７年である。８４Ｇの寿命制限因子とし
ては、ＢＩＧの減少とＢ４ＣのスウェリングによるＳＯ
３３０４ステンレス鋼被覆の破損を挙げることができる
。Currently, boron carbide (84C), Ag-15% In-5% Cd are used as control materials for light water-cooled nuclear reactors.
Alloys are used. Of these, the latter is gradually decreasing due to economic reasons, and the former has become the mainstream. B4C is used as a control material packed in stainless steel tubes in powder or pellet form and has an average lifespan of 4 to 7 years. The life-limiting factors of 84G are SO due to BIG decrease and B4C swelling.
Failure of the 3304 stainless steel coating can be mentioned.
最近の原子炉の運転方法は、制御棒の移動を最少にする
方向にあり、高密度の中性子束に長期間さらされるので
、中性子吸収能の劣化の少い長寿命の制御材料の開発が
要求されている。Recent operating methods for nuclear reactors are aimed at minimizing the movement of control rods, and as they are exposed to high-density neutron flux for long periods of time, there is a need for the development of long-life control materials with less deterioration in neutron absorption capacity. has been done.
ハフニウム（Ｈｆ）は、その有望な材料の一つであり、
ＰＷＲ環境（３２０℃、加圧水）では良好な特性を示し
ているがＢＷＲ環境（２９０℃、沸騰水）下では必ずし
も充分な耐食性を有していない。Hafnium (Hf) is one of the promising materials,
Although it shows good properties in a PWR environment (320°C, pressurized water), it does not necessarily have sufficient corrosion resistance in a BWR environment (290°C, boiling water).
本発明は斯かる問題に鑑み、ＢＷＲ環境下でも高温高圧
の水、水蒸気に対し充分な耐食性を有するハフニウム合
金を提供とすることを目的とする。In view of such problems, the present invention aims to provide a hafnium alloy that has sufficient corrosion resistance against high temperature and high pressure water and steam even in a BWR environment.
（問題点を解決するための手段）
上記目的を達成するために、中性子吸収能の優れたＩｆ
にその特性を害さない範囲でＦｅまたは／およびＮｂを
添加し、かつＦｅ ＋ Ｎｂ ： ０．０２〜７．０重
量％としてＨｆを合金化し、耐食性を著しく向上させた
。(Means for solving the problem) In order to achieve the above purpose, If
The corrosion resistance was significantly improved by adding Fe or/and Nb to the alloy within a range that does not impair its properties, and by setting Fe + Nb: 0.02 to 7.0% by weight to form an alloy with Hf.
（実施例）
本発明に係るＨｆ合金は、Ｆｅまたは／およびＮｂと残
部実質的にｌｌｆとからなり、Ｆｅ ＋ Ｎｂ ： ０
．０２〜７．０重量％とじたものである。Ｆｅ ＋ Ｎ
ｂの成分限定理由は下記の通りである。(Example) The Hf alloy according to the present invention consists of Fe or/and Nb and the balance substantially Ilf, Fe + Nb: 0
．． 02 to 7.0% by weight. Fe+N
The reason for limiting the component b is as follows.
ＰｅおよびＮｂは、）Ｉｆの高温高圧の水、水蒸気に対
する耐食性を改善する作用をなす。耐食性の向上には、
黒色密着性を有する酸化被膜が寄与し、この被膜を形成
させるためには、（Ｆｅ ＋ Ｎｂ）量を０゜０２％以
上にする必要がある。Pe and Nb serve to improve the corrosion resistance of )If against high-temperature, high-pressure water and steam. To improve corrosion resistance,
In order to contribute to the formation of an oxide film having black adhesion, the amount of (Fe + Nb) needs to be 0°02% or more.
（Ｆｅ ＋ Ｎｂ）量が０．０２％以上で耐食性は一定
となるが、（Ｆｅ ＋ Ｎｂ）量の増加と共に加工性が
悪化し、８％以上では加工が困難になる。When the amount of (Fe + Nb) is 0.02% or more, the corrosion resistance becomes constant, but as the amount of (Fe + Nb) increases, the workability deteriorates, and when the amount of (Fe + Nb) is more than 8%, it becomes difficult to work.
また、Ｆｅ、 Ｎｂの熱中性子吸収断面積は、Ｈｆと比
べて小さく、制御材料として中性子吸収能を著しく損な
わないためには、（ｐｅ＋Ｎｂ） Ｉを７％以下に制服
する必要がある。In addition, the thermal neutron absorption cross section of Fe and Nb is smaller than that of Hf, and in order to not significantly impair the neutron absorption ability as a control material, it is necessary to keep (pe+Nb)I at 7% or less.
尚、実質的なＨｆとは９５％程度の高純度＋１ｆを指称
するものである。他の主な不純物はＺｒである。Note that "substantial Hf" refers to high purity +1f of about 95%. The other main impurity is Zr.
次に、本発明の具体的実施例を比較例と共に掲げて説明
する。Next, specific examples of the present invention will be described together with comparative examples.
高純度ＩｆｆにＦｅ又は／およびＮｂを添加して種々の
（Ｆｅ ＋ Ｎｂ）％を有するＨｆ合金を熔製し、５鰭
厚のスラブに鋳造し、得られたスラブを冷間圧延して１
酊厚のＨｆ合金板を製作した。Hf alloys with various (Fe + Nb) percentages are melted by adding Fe or/and Nb to high-purity Iff, cast into slabs with a thickness of 5 fins, and the resulting slabs are cold-rolled into 1.
A thick Hf alloy plate was manufactured.
このｌｌｆＨｆ合金板いて、静置式オートクレーブ試験
装置を使用して５００°Ｃ，１０５気圧の高温高圧の水
蒸気中で２４時間加圧して耐食性を調べた。その結果を
第１図に示す。第１図より、高純度１１ｆの耐食性は良
くないが（Ｆｅ＋Ｎｂ）％が０．０２％以上で優れた耐
食性を示すことが判る。This IlfHf alloy plate was pressurized in high-temperature, high-pressure water vapor at 500°C and 105 atm for 24 hours using a static autoclave tester to examine its corrosion resistance. The results are shown in FIG. From FIG. 1, it can be seen that although the corrosion resistance of high-purity 11f is not good, it exhibits excellent corrosion resistance when the (Fe+Nb)% is 0.02% or more.
また、Ｈｆ合金板の製作過程において、冷間加工性が観
察された。その結果を第２図に示す。高純度Ｈｆは冷間
加工性に劣るが、（Ｆｅ＋Ｎｂ）の添加と共に加工性は
改良され、（Ｆｅ ＋ Ｎｂ）が０．１〜１％で優れた
加工性を示す。（Ｐｅ ＋ Ｎｂ） ６度がさらに増加
すると、材料の硬化が生じる。８％を越えると加工性の
劣化が著しい。In addition, cold workability was observed during the manufacturing process of the Hf alloy plate. The results are shown in FIG. Although high-purity Hf has poor cold workability, the workability is improved with the addition of (Fe + Nb), and exhibits excellent workability when (Fe + Nb) is 0.1 to 1%. Further increases in (Pe + Nb) 6 degrees result in hardening of the material. If it exceeds 8%, the deterioration of workability is significant.
第１図及び第２図より、本発明に係るＦｅ＋Ｎｂ：０．
０２〜７．０％のハフニウム合金は、耐食性及び加工性
が共に優れていることが＠認された。From FIG. 1 and FIG. 2, Fe+Nb according to the present invention: 0.
It was found that the hafnium alloy containing 0.02% to 7.0% has excellent corrosion resistance and workability.
（発明の効果）
以上説明したように、本発明のハフニウム合金は、その
合金成分であるＦｅまたは／およびＮｂをＦｅ＋Ｎｂ
： ０．０２〜７．０重量％に特定したので、加工性及
び中性子吸収性を損なうことなく優れた耐食性を付与す
ることができた。このように本発明のハフニウム合金は
耐食性に極めて優れるのでＢＷＲ環境下でも充分使用で
き、実質的価値は著大である。(Effects of the Invention) As explained above, the hafnium alloy of the present invention replaces its alloy components Fe and/or Nb with Fe+Nb.
: Since the content was specified at 0.02 to 7.0% by weight, excellent corrosion resistance could be imparted without impairing processability and neutron absorption. As described above, the hafnium alloy of the present invention has extremely excellent corrosion resistance, so it can be used satisfactorily even in a BWR environment, and has great practical value.
第１図は５００℃における耐食性を示す図であって、（
Ｆｅ ＋ Ｎｂ） ’ｔａ度と腐食増量との関係を示す
グラフ図、第２図は（Ｆｅ ＋ Ｎｂ）濃度と冷間加工
性との関係を示すグラフ図である。FIG. 1 is a diagram showing corrosion resistance at 500°C, (
Fig. 2 is a graph showing the relationship between (Fe + Nb) concentration and cold workability.
Claims (1)
ｅ＋Ｎｂ：０．０２〜７．０％ であり、残部が実質的にＨｆであることを特徴とする耐
食ハフニウム合金。[Claims] 1. Chemical composition is by weight %, Fe or/and Nb is F
A corrosion-resistant hafnium alloy characterized in that e+Nb: 0.02 to 7.0%, with the remainder being substantially Hf.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3154286A JPS62188744A (en) | 1986-02-14 | 1986-02-14 | Corrosion resistant hafnium alloy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3154286A JPS62188744A (en) | 1986-02-14 | 1986-02-14 | Corrosion resistant hafnium alloy |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62188744A true JPS62188744A (en) | 1987-08-18 |
Family
ID=12334076
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3154286A Pending JPS62188744A (en) | 1986-02-14 | 1986-02-14 | Corrosion resistant hafnium alloy |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62188744A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03236453A (en) * | 1990-02-13 | 1991-10-22 | Sumitomo Metal Ind Ltd | Seamless hafnium tube and its production |
| WO1994028185A1 (en) * | 1993-05-25 | 1994-12-08 | Electric Power Research Institute | Hafnium alloys as neutron absorbers |
-
1986
- 1986-02-14 JP JP3154286A patent/JPS62188744A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03236453A (en) * | 1990-02-13 | 1991-10-22 | Sumitomo Metal Ind Ltd | Seamless hafnium tube and its production |
| WO1994028185A1 (en) * | 1993-05-25 | 1994-12-08 | Electric Power Research Institute | Hafnium alloys as neutron absorbers |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US5080861A (en) | Corrosion resistant zirconium alloy | |
| KR0178757B1 (en) | Rod for a fuel assembly of a nuclear reactor resisting corrosion and wear | |
| CN103898368B (en) | Zirconium-based alloy for nuclear fuel assembly | |
| JPH07224373A (en) | Method of improving corrosion resistance of barrier coating made of zirconium or zirconium alloy | |
| US5892807A (en) | Pressurized water reactor nuclear fuel assembly | |
| JPH11202072A (en) | Nuclear fuel particle for reactor, nuclear fuel pellet and element | |
| JPS62188744A (en) | Corrosion resistant hafnium alloy | |
| CN106929706A (en) | A kind of zirconium-base alloy in the hot environment for nuclear reactor | |
| US5790623A (en) | Composite cladding for nuclear fuel rods | |
| Sridharan | Understanding how materials corrode in nuclear reactors | |
| JPH04224648A (en) | High corrosion resistant and high strength zirconium alloy | |
| US3431104A (en) | Zirconium base alloy | |
| JPS6333535A (en) | Zirconium alloy for nuclear reactor | |
| EP0745258B1 (en) | A nuclear fuel element for a pressurized water reactor and a method for manufacturing the same | |
| JPS60256084A (en) | Composite type zirconium alloy coated pipe | |
| US5772798A (en) | High strength zirconium alloys containing bismuth | |
| JPH01188643A (en) | Zr alloy for covering tube of atomic reactor fuel having excellent corrosion resistance | |
| Kim et al. | Internal hydriding of defected Zircaloy cladding fuel rods: a review | |
| Farina et al. | Current status of Zirconium alloys for fission cladding | |
| EP0964407B1 (en) | High strength zirconium alloys containing bismuth, tin and niobium | |
| EP0964406A1 (en) | High strength zirconium alloys containing bismuth and niobium | |
| JPH01242746A (en) | Corrosion-resistant zirconium alloy | |
| JPH07150275A (en) | Highly corrosion resistant zirconium-base alloy | |
| JPS6217146A (en) | Corrosion-resistant zirconium alloy | |
| JPS62207835A (en) | Zr alloy having superior nodular corrosion resistance |