JPH0337596A - Nuclear fuel element - Google Patents
Nuclear fuel elementInfo
- Publication number
- JPH0337596A JPH0337596A JP1171136A JP17113689A JPH0337596A JP H0337596 A JPH0337596 A JP H0337596A JP 1171136 A JP1171136 A JP 1171136A JP 17113689 A JP17113689 A JP 17113689A JP H0337596 A JPH0337596 A JP H0337596A
- Authority
- JP
- Japan
- Prior art keywords
- layer
- cladding tube
- zirconium
- nuclear fuel
- stress
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 19
- 238000005253 cladding Methods 0.000 claims abstract description 32
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims abstract description 24
- 229910052726 zirconium Inorganic materials 0.000 claims abstract description 24
- 239000000446 fuel Substances 0.000 claims abstract description 18
- 239000008188 pellet Substances 0.000 claims abstract description 17
- 239000000956 alloy Substances 0.000 claims abstract description 5
- 229910045601 alloy Inorganic materials 0.000 claims abstract description 5
- 239000010409 thin film Substances 0.000 claims abstract description 3
- 239000010410 layer Substances 0.000 claims description 25
- 239000011247 coating layer Substances 0.000 claims description 15
- 239000010408 film Substances 0.000 claims 1
- 230000007797 corrosion Effects 0.000 abstract description 31
- 238000005260 corrosion Methods 0.000 abstract description 31
- 229910052782 aluminium Inorganic materials 0.000 abstract description 10
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract description 9
- 229910052793 cadmium Inorganic materials 0.000 abstract description 2
- 238000005336 cracking Methods 0.000 description 11
- 230000004992 fission Effects 0.000 description 9
- 238000007747 plating Methods 0.000 description 7
- 230000000694 effects Effects 0.000 description 6
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 238000007740 vapor deposition Methods 0.000 description 3
- 239000004411 aluminium Substances 0.000 description 2
- 230000003993 interaction Effects 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000010419 fine particle Substances 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000005245 sintering Methods 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
Landscapes
- Other Surface Treatments For Metallic Materials (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用９町」
本発明は、ＪｊＫ了炉用核燃判里素に係り、特にジル−
ｌニラムラ・ｆす被覆管のさら１こ内層側に第２層の薄
１１急を設けることにより、耐食性の向上に灯適松核燃
判要素に関する。[Detailed description of the invention] [Industrial use in 9 towns] The present invention relates to nuclear fuel dispersion for JJK reactors, and in particular
By providing a second thin layer on the inner layer side of the cladding tube, corrosion resistance can be improved.
［従来の技術］
現行の軽水路で使用されている原子炉用核燃料要素は、
核燃料粉末を円柱状に焼結した燃料ペレッ［・をジルコ
ニウム基合金の被覆管内に装填し、ヘリウムガスを刺入
して、」二、下部を端栓て密封されている。[Prior art] Nuclear fuel elements for nuclear reactors currently used in light waterways are:
Fuel pellets made by sintering nuclear fuel powder into a cylindrical shape are loaded into a zirconium-based alloy cladding tube, helium gas is introduced, and the bottom is sealed with an end plug.
原子炉の使用時には、燃料ペレツＩ〜は半径方向に大き
な温度勾配（約２′Ｏ○°Ｃ／１■）が生じるため、上
下端が外側に張出し、つづみ形に変形する。When a nuclear reactor is used, the fuel pellets I~ undergo a large temperature gradient in the radial direction (approximately 2'O°C/1■), so the upper and lower ends thereof bulge outward and deform into a chain shape.
特に、変形量の大きいペレット端面部が被覆管に接触す
ると被覆管に高い応力と歪みを与えることになる（ベー
ン１−−被覆管の力学的相互作用（■）ＣＭＴ）という
）。ぺＩノソｌ一端面部と被覆管が接触し、高い応力と
歪みの集中した個所は燃料ベレンＩ〜かｌ）放出された
腐食性の核分裂生成物が作用すると、応力腐食割れを起
こす可能性かあると言われている。応力と歪みの集中は
応力腐食割れの可能性を増大する。In particular, when the end face of the pellet having a large amount of deformation comes into contact with the cladding tube, high stress and strain will be applied to the cladding tube (referred to as vane 1 - mechanical interaction of the cladding (■) CMT). There is a possibility that stress corrosion cracking will occur if the emitted corrosive fission products act on the area where the end surface of the cladding tube contacts and high stress and strain are concentrated. It is said that there is. Stress and strain concentrations increase the likelihood of stress corrosion cracking.
応力腐食割れ防止の観点から被覆管内表面にジルコニラ
１１を被覆したジルコニウ１３ライナ被覆管においては
、バレン１〜の変形によるペレット端面部と被覆管との
接触によって生しる応力と歪みを、被覆管内表面に被覆
したジルコニラ１１を変形させることによって緩和し、
耐応力腐食割れ性の向上が図られている。In order to prevent stress corrosion cracking, the inner surface of the cladding tube is coated with zirconium 13 liner cladding tube. Relaxed by deforming the zirconia 11 coated on the surface,
Efforts are being made to improve stress corrosion cracking resistance.
［発明が解決しようとする課題］
ジルコニウムライナ被覆管においては、原子炉運転中の
被覆管内で発生しつつある応力と歪みの緩和は図られる
が、腐食性の核分裂生成物による被覆管内表面の腐食、
特に■、Ｃｓ、Ｃａ等による結晶粒界の選択的な腐食は
防止できない。[Problems to be Solved by the Invention] Zirconium liner cladding can alleviate the stress and strain that is occurring within the cladding during reactor operation, but corrosion of the inner surface of the cladding due to corrosive fission products occurs. ,
In particular, selective corrosion of grain boundaries due to (1), Cs, Ca, etc. cannot be prevented.
本発明の目的は、上記問題点を解決し、腐食性の核分裂
生成物による耐応力腐食割れ性を向上し、高燃焼度に耐
える原子炉用核燃料要素を提０（することにある。An object of the present invention is to solve the above-mentioned problems and provide a nuclear fuel element for a nuclear reactor that has improved resistance to stress corrosion cracking due to corrosive fission products and can withstand high burn-up.
［課題を解決するための手段］
上記課題を解決するための本発明に係る核燃料要素の横
取は、ジルコニウム」１（合金からなる核燃料被覆管の
内面に純ジルコニウム層を設けたライナ被覆管内に、複
数個の燃料ペレットを積層して収納し、その上１；両端
を端栓により密封してなる核燃料要素において、ライナ
被覆管の内側に、第２層とし７て、Ａｌの薄膜を形成す
るようにしたことである。[Means for Solving the Problems] In order to solve the above-mentioned problems, the seizure of nuclear fuel elements according to the present invention is based on the method of stealing nuclear fuel elements in a liner cladding tube in which a pure zirconium layer is provided on the inner surface of a nuclear fuel cladding tube made of zirconium 1 (alloy). In a nuclear fuel element in which a plurality of fuel pellets are stacked and stored, and both ends are sealed with end plugs, a thin film of Al is formed as a second layer 7 inside the liner cladding tube. This is what I did.
［作用］
原子炉使用時の核燃料要素においては、燃料ペレソＩ・
は半径方向に大きな温度勾配が生しるため、ペレッ１へ
の上下端が外側に張出し、つづみ形に変形して、ペレッ
ト端面部が被覆管に接触し、被覆管に高い応力と歪みを
与えるようになる。ペレット端面ｆ１１；と被覆管が接
触し、高い応力と歪みの集中した個所に燃料ペレットか
ら放出された腐食性の核分裂生成物（Ｆｌ〕）が作用す
ると、応力腐食割れを起こす可能性が増大する。応力腐
食割れを防止する方法として、従来から種々の考案が提
出されているが十分満足の行くものではなかった。[Function] In nuclear fuel elements when used in a nuclear reactor, fuel pereso I.
Since a large temperature gradient occurs in the radial direction, the upper and lower ends of pellet 1 protrude outward, deform into a pinched shape, and the end surface of the pellet comes into contact with the cladding tube, causing high stress and strain on the cladding tube. Start giving. When the pellet end face f11 comes into contact with the cladding tube and the corrosive fission products (Fl) released from the fuel pellet act on the area where high stress and strain are concentrated, the possibility of stress corrosion cracking increases. . Various ideas have been proposed in the past as methods for preventing stress corrosion cracking, but none have been fully satisfactory.
すてに実施されているジルコニウムライナ被覆管におい
ては、従来のジルコニウム基被覆管の内面に純ジルコニ
ウム層を設けて、燃料ベレッＩ・とのＰ ＣＭ Ｉを低
減させるのに有効である。In conventional zirconium liner cladding, a layer of pure zirconium is provided on the inner surface of a conventional zirconium-based cladding, which is effective in reducing PCM I with fuel bellet I.
本発明のように第２層として、例えばＡｌＪ）を、メツ
キあるいは蒸着によって形成することによって、Ｔ２、
Ｃｓ、ＣｄなとのＦＰガスによる結晶粒界の選択的腐食
を防止し、耐ＳＣＣ性の向上を図ろうとするものである
。As in the present invention, by forming a second layer (for example, AlJ) by plating or vapor deposition, T2,
The purpose is to prevent selective corrosion of grain boundaries caused by FP gases such as Cs and Cd, and to improve SCC resistance.
第２ＭとしてＡｌを用いた効用について説明する。The effect of using Al as the second M will be explained.
（１）Ａｌは、Ｃｕ、Ａ、ｕなどと同様に延展性に富ん
でいる。(1) Al, like Cu, A, u, etc., is highly ductile.
（２）ＦＰガス（■２、Ｃｓ、Ｃ８など）に対して耐食
性がよい。ＣｕおよびＡｌの試料を用いて、１□に対す
る耐食性試験を実施した結果は、Ａｌは、約３倍の耐食
性があることを確認した。(2) Good corrosion resistance against FP gas (■2, Cs, C8, etc.). The results of a corrosion resistance test for 1□ using Cu and Al samples confirmed that Al has about three times the corrosion resistance.
（３）第２ＪｊｌにＡｌメツキを施こしたライナ被覆管
を原子炉内で使用すると、燃料ペレッ１〜Ｔ、Ｊ○２か
ら生ずる０２と反応して表面に耐食性の富んだＡｌ２０
３が形成される。(3) When a liner cladding tube with Al plating applied to the second Jjl is used in a nuclear reactor, it reacts with 02 generated from fuel pellets 1 to T and J○2, forming Al20 with high corrosion resistance on the surface.
3 is formed.
（４）Ａｌは、安価であり、容易に入手することができ
る。(4) Al is inexpensive and easily available.
つきに、へΩメツキ層の厚さについては、すでに実験に
より確めたＣｕの場合に、使用期間中（約１年間）に生
成する■２との反応では、５〜１０μｍで、有効なるこ
とを確かめた。Finally, regarding the thickness of the ohm plating layer, in the case of Cu, which has already been confirmed through experiments, a thickness of 5 to 10 μm is effective in the reaction with I confirmed that.
また、被覆管内におけるＵＯ□ペレットとのギャップを
考慮してＡｌメツキ層の場合も５〜↓Ｏμｍとした。Further, in consideration of the gap between the UO□ pellet in the cladding tube, the thickness of the Al plating layer was set to 5 to ↓O μm.
すなわち、ジルコニウムライナ管の第３−Ｍのジルコニ
ラ１１は延性に富み、変形しやすいため、ペレット端面
部に生しる応力や歪みを吸収して、応力集中を緩和する
作用があり、第２被覆層のアルミニラ１１のメツキ層あ
るいは蒸着層は第１被覆層のジルコニウム等を保護し、
腐食性核分裂生成物による選択的な腐食を防止すること
ができる。さらに、アルミニウムは延性に富み、変形し
やすいため、応力集中を緩和する作用がある。In other words, the 3-M zirconia 11 of the zirconium liner tube has high ductility and is easily deformed, so it has the effect of absorbing stress and distortion occurring at the end face of the pellet and alleviating stress concentration. The plating layer or vapor deposition layer of the aluminium 11 layer protects the zirconium etc. of the first coating layer,
Selective corrosion by corrosive fission products can be prevented. Furthermore, since aluminum is highly ductile and easily deformed, it has the effect of alleviating stress concentration.
以上のような作用によって、腐食性核分裂生成物による
選択的腐食の防出及びペレット端面部と被覆管の接触に
よる応力集中の緩和がなされ、応力腐食割れの防止が可
能となる。The above actions prevent selective corrosion caused by corrosive fission products and alleviate stress concentration caused by contact between the end face of the pellet and the cladding tube, making it possible to prevent stress corrosion cracking.
［実施例］
以下、本発明に係わる一実胤例を図面を用いて説明する
。[Example] Hereinafter, an example of a seed according to the present invention will be explained using the drawings.
図面は、核燃料要素の横取をノｊｅしたものである。The drawing shows the seizure of nuclear fuel elements.
核燃料要素は、ジルコニウム基合金よりなる彼覆％ｉと
、被覆管」の内表面に純ジルコニウム層２を成形し、さ
らに純ジルコニウ１１層２の上にアルミニウムのメツキ
層あるいは蒸着層からなる第２被覆層３と、燃料ペレノ
１〜４から成っている。The nuclear fuel element is formed by forming a pure zirconium layer 2 on the inner surface of the cladding made of a zirconium-based alloy and a cladding tube, and further forming a second layer made of a plated or vapor-deposited layer of aluminum on the pure zirconium 11 layer 2. It consists of a coating layer 3 and fuel perenos 1 to 4.
被覆層の厚さは、純ジルコニウ１１層２はペレット−燃
料の力学的相互作用の低減を目的としているため、５０
〜１００μ丁ｎ必要であり、第２被覆層３は第１被覆層
２の選択的な腐食の防止が１″１的であるため、燃料の
使用期間（約１ケ年）の間に摩耗、破損しなければよい
ので、５〜１０μｍで十分である。The thickness of the coating layer is 50 mm because the pure zirconium 11 layer 2 is intended to reduce the mechanical interaction between the pellet and the fuel.
The second coating layer 3 only prevents selective corrosion of the first coating layer 2 by 1", so it will not wear out during the period of use of the fuel (approximately 1 year). As long as it does not cause damage, a thickness of 5 to 10 μm is sufficient.
原子炉使用時の核燃料要素においては、燃料ベーン１〜
は半径方向に大きな温度勾配が生じるため、上−ド端か
外側に張出し、っづみ形に変形して、燃料ペレソト４端
面部が被覆管に接触し、被覆管１に高い応力と歪みを与
えるようになるが、第１被覆層２、第２被覆層３に用い
るジルコニウム、アルミニラ１１は延性に富み、変形し
やすいため、第１被覆層２、第２被覆層３が変形して応
力緩和が生しる。一方、腐食性核分裂生成物による純ジ
ルコニウム層２の選択的腐食はアルミニウムからなる第
２被覆層３を設けることによって防止される。In nuclear fuel elements when using a nuclear reactor, fuel vanes 1 to
Since a large temperature gradient occurs in the radial direction, the upper end of the fuel pipe protrudes outward and deforms into a wedge shape, causing the end face of the fuel plate 4 to come into contact with the cladding tube, giving high stress and strain to the cladding tube 1. However, since the zirconium and aluminium 11 used for the first coating layer 2 and the second coating layer 3 are highly ductile and easily deformed, the first coating layer 2 and the second coating layer 3 are deformed and stress relaxation occurs. Live. On the other hand, selective corrosion of the pure zirconium layer 2 by corrosive fission products is prevented by providing the second coating layer 3 made of aluminum.
第２被覆層３に用いるアルミニウムは腐食性核分裂生成
物との共存性が良く、またメツキ層あるいは蒸着層は微
粒子から形成されているので選択的な腐食は生じ難く、
全般的に耐食性は改善される。The aluminum used for the second coating layer 3 has good coexistence with corrosive fission products, and since the plating layer or vapor deposition layer is formed from fine particles, selective corrosion is difficult to occur.
Corrosion resistance is generally improved.
以」−１第２被覆層としてＡｌについては説明したが、
Ａｕについても、延展性がすぐれ、ＦＰ外ガス対する耐
食性がよいなどの点て、第２被覆層として使用すること
ができる。-1 Although Al has been explained as the second coating layer,
Au can also be used as the second coating layer because it has excellent spreadability and good corrosion resistance against gas outside the FP.
本実施例による効果は、以」―のように応力腐食割れの
原円となる応力集中や選択的腐食が緩和されることから
、応力腐食割れを軽減することにある。The effect of this embodiment is to reduce stress corrosion cracking since stress concentration and selective corrosion, which are the origin of stress corrosion cracking, are alleviated as described below.
［発明の効果］
本発明によれば、原子炉使用時における燃料ペレ
ット
む金属の変形によって吸収し、応力集中を緩和し、さら
に被覆した金属は腐食性核分裂生成物との共存性が良い
こと及びメツキ層あるいは蒸着層が選択的腐食を受けな
いことから、耐食性が改善され、総じて応力腐食割れを
軽減することが可能となる。[Effects of the Invention] According to the present invention, stress concentration is absorbed by the deformation of the metal contained in fuel pellets during use of a nuclear reactor, and the coated metal has good coexistence with corrosive fission products. Since the plating layer or the vapor deposited layer does not undergo selective corrosion, corrosion resistance is improved and stress corrosion cracking can be reduced overall.
このことは、核燃料要素の長寿命化、高燃焼度化に効果
があり、燃料経済性にも大きく貢献することになる。This has the effect of extending the life of nuclear fuel elements and increasing burnup, and greatly contributes to fuel economy.
図面は、本発明に係り第２被′Ｆ！Ｉ層を設けた核燃料
要素の断面図である。
く符号の説明〉
■ 核燃料被覆管、２ ・純ジルコニウム層、３・第２
被覆層、４ 燃料ペレット。The drawings show the second aspect of the present invention. 1 is a cross-sectional view of a nuclear fuel element provided with an I layer; FIG. Explanation of symbols> ■ Nuclear fuel cladding tube, 2 ・Pure zirconium layer, 3 ・Second
Coating layer, 4 fuel pellets.
Claims (1)
純ジルコニウム層を設けたライナ被覆管内に、複数個の
燃料ペレットを積層して収納し、その上下両端を端栓に
より密封してなる核燃料要素において、ライナ被覆管の
内側に、第２層として、Ａｌの薄膜を形成したことを特
徴とする核燃料要素。 ２、第２被覆層として形成するＡｌ薄膜の厚さを、５〜
１０μｍにしたことを特徴とする請求項１記載の核燃料
要素。[Claims] 1. A plurality of fuel pellets are stacked and stored in a liner cladding tube made of a zirconium-based alloy with a pure zirconium layer provided on the inner surface, and both upper and lower ends are sealed with end plugs. A nuclear fuel element comprising: a thin Al film formed as a second layer on the inside of a liner cladding tube. 2. The thickness of the Al thin film formed as the second coating layer is 5 to 5.
The nuclear fuel element according to claim 1, characterized in that it has a diameter of 10 μm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1171136A JPH0337596A (en) | 1989-07-04 | 1989-07-04 | Nuclear fuel element |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1171136A JPH0337596A (en) | 1989-07-04 | 1989-07-04 | Nuclear fuel element |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0337596A true JPH0337596A (en) | 1991-02-18 |
Family
ID=15917655
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1171136A Pending JPH0337596A (en) | 1989-07-04 | 1989-07-04 | Nuclear fuel element |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0337596A (en) |
-
1989
- 1989-07-04 JP JP1171136A patent/JPH0337596A/en active Pending
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