JPH0321077B2 - - Google Patents
Info
- Publication number
- JPH0321077B2 JPH0321077B2 JP57099406A JP9940682A JPH0321077B2 JP H0321077 B2 JPH0321077 B2 JP H0321077B2 JP 57099406 A JP57099406 A JP 57099406A JP 9940682 A JP9940682 A JP 9940682A JP H0321077 B2 JPH0321077 B2 JP H0321077B2
- Authority
- JP
- Japan
- Prior art keywords
- end plug
- oxygen diffusion
- diffusion layer
- zirconium
- corrosion
- 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 - Lifetime
Links
- 239000001301 oxygen Substances 0.000 claims description 32
- 229910052760 oxygen Inorganic materials 0.000 claims description 32
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 31
- 238000009792 diffusion process Methods 0.000 claims description 28
- 239000000956 alloy Substances 0.000 claims description 20
- 229910045601 alloy Inorganic materials 0.000 claims description 20
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 19
- 229910052726 zirconium Inorganic materials 0.000 claims description 19
- 239000000446 fuel Substances 0.000 claims description 12
- 238000005260 corrosion Methods 0.000 description 25
- 230000007797 corrosion Effects 0.000 description 25
- 239000010410 layer Substances 0.000 description 23
- 239000000463 material Substances 0.000 description 7
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 6
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 6
- 239000001257 hydrogen Substances 0.000 description 6
- 229910052739 hydrogen Inorganic materials 0.000 description 6
- 238000000034 method Methods 0.000 description 5
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 4
- 238000005253 cladding Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 238000010438 heat treatment Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 4
- 239000008188 pellet Substances 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 3
- 150000004678 hydrides Chemical class 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- 229910052759 nickel Inorganic materials 0.000 description 3
- 239000000758 substrate Substances 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 2
- ATJFFYVFTNAWJD-UHFFFAOYSA-N Tin Chemical compound [Sn] ATJFFYVFTNAWJD-UHFFFAOYSA-N 0.000 description 2
- 229910052804 chromium Inorganic materials 0.000 description 2
- 239000011651 chromium Substances 0.000 description 2
- 238000005520 cutting process Methods 0.000 description 2
- 229910052742 iron Inorganic materials 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000010894 electron beam technology Methods 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910052758 niobium Inorganic materials 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 150000002926 oxygen Chemical class 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- 239000007858 starting material Substances 0.000 description 1
- 239000002344 surface layer Substances 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Fuel-Injection Apparatus (AREA)
Description
【発明の詳細な説明】
〔発明の属する技術分野〕
本発明はジルコニウム基合金から成る燃料棒の
端栓に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of the Invention] The present invention relates to a fuel rod end plug made of a zirconium-based alloy.
軽水炉に使用される燃料集合体は、第１図に一
部切欠縦断面図として示すように主として上部タ
イプレート１、下部タイプレート２、および核燃
料ペレツトUO2を含む複数の燃料棒３、および１
本のウオーターロツトとこれらを収納するチヤン
ネルボツクス４から成る。燃料棒３の形状を第２
図に縦断面図で示す。
A fuel assembly used in a light water reactor mainly includes an upper tie plate 1, a lower tie plate 2, and a plurality of fuel rods 3 containing nuclear fuel pellets UO 2 , as shown in FIG.
It consists of a book waterlot and 4 channel boxes to store them. The shape of the fuel rod 3 is
The figure shows a longitudinal cross-sectional view.
燃料棒３は、被覆管５、核燃料ペレツトUO2
６、プレナムスプリング７、上部端栓８、および
下部端栓９からなる。また、ウオーターロツド
は、内部にUO2を含まない管で細孔が設けられ、
内部に冷却水が通るようになつており、燃料棒と
同様に上、下部端栓により上、下部タイプレート
に支持されている。 The fuel rod 3 includes a cladding tube 5 and a nuclear fuel pellet UO 2.
6, a plenum spring 7, an upper end plug 8, and a lower end plug 9. In addition, the water rod is a tube that does not contain UO 2 and has pores inside.
Cooling water is allowed to flow inside, and like the fuel rods, they are supported by upper and lower tie plates by upper and lower end plugs.
さて、上記端栓の材料としては通常ジルコニウ
ムに重量比で錫を1.2〜1.7％、鉄を0.07〜0.20％、
クロムを0.05〜0.15％、ニツケルを0.03〜0.08％
添加して成るジルカロイ−２と呼称されるジルコ
ニウム基合金が使用されている。 Now, the materials for the end plugs mentioned above are usually zirconium with a weight ratio of 1.2 to 1.7% tin and 0.07 to 0.20% iron.
0.05-0.15% chromium, 0.03-0.08% nickel
A zirconium-based alloy called Zircaloy-2 is used.
ところが、長期間の実装運転において、ノジユ
ラーコロージヨンと呼ばれる腐食反応による斑点
状の白色生成物が端栓表面に生成することがあ
る。上記白色生成物がノジユラーコロージヨンの
進展に伴い次第に成長すると端栓はわずかながら
肉減りし端栓の機械的強度の低下を招来する恐れ
がある。さらに炉内滞留時間を延長した場合、上
記ノジユラーコロージヨンによる肉減りに加え
て、端栓とタイプレートに穿孔された支持孔との
摺動摩耗による端栓の肉減りのおそれもあること
から一層良好な機械的特性と耐ノジユラーコロー
ジヨン性とを有するジルコニウム基合金から成る
燃料棒の端栓が要望されている。 However, during long-term mounting operation, speckled white products due to a corrosion reaction called nodular corrosion may be formed on the surface of the end plug. If the white product gradually grows as the nodular corrosion develops, the end plug may become slightly thinner, leading to a decrease in the mechanical strength of the end plug. Furthermore, if the residence time in the furnace is extended, in addition to the thinning caused by the nodular corrosion described above, there is also the risk of thinning of the end plug due to sliding wear between the end plug and the support hole drilled in the tie plate. There is a need for fuel rod end plugs made from zirconium-based alloys that have better mechanical properties and nodular corrosion resistance.
本発明は、上記事情に鑑みなされたもので、優
れた機械的特性とすぐれた耐ノジユラーコロージ
ヨン性を有する燃料棒の端栓を提供するものであ
る。
The present invention was made in view of the above circumstances, and provides a fuel rod end plug having excellent mechanical properties and excellent nodular corrosion resistance.
ジルコニウム基合金におけるノジユラーコロー
ジヨンの主要反応は、ジルコニウム基合金内での
水素化物生成反応であり、従つて何らかの手段に
やりジルコニウム基合金基体内部に水素が侵入す
ることを防ぎ水素化物の生成を防止あるいは制御
し得ればノジユラーコロージヨンの発生を阻止乃
至軽減し得る事に着目し、
本発はジルコニウム基合金から成る燃料棒の端
栓の少なくとも表面に酸素拡散層を形成しておく
と、この酸素拡散層が水素の侵入に対する障壁に
なり端栓のノジユラーコロージヨンに対する耐食
性の向上に寄与するばかりでなく、酸素拡散層と
いう比較的高濃度の酸素を含有する層が端栓の表
面または表面近傍に存在することにより、耐摩耗
性などの機械的性質を向上させることに着目して
なされたものである。
The main reaction of nodular corrosion in a zirconium-based alloy is a hydride-forming reaction within the zirconium-based alloy. Therefore, it is necessary to prevent hydrogen from penetrating into the zirconium-based alloy substrate by some means to prevent the formation of hydrides. Alternatively, focusing on the fact that the occurrence of nodular corrosion can be prevented or reduced if it can be controlled, the present invention proposes that if an oxygen diffusion layer is formed on at least the surface of the end plug of a fuel rod made of a zirconium-based alloy, This oxygen diffusion layer not only acts as a barrier against hydrogen intrusion and contributes to improving the corrosion resistance of the end plug against nodular corrosion, but also that the oxygen diffusion layer, a layer containing a relatively high concentration of oxygen, is formed on the surface of the end plug or This was done with the aim of improving mechanical properties such as wear resistance by being present near the surface.
以下に本発明に係る実施例を示す。 Examples according to the present invention are shown below.
ジルカロイ−２のインゴツトを出発原料として
ASTM規格B351−79に従つてロツド材を製造
し、このロツド材に切削加工等を施して端栓形状
に加工した後、酸素拡散処理を施して第３図に側
面図として示すようにジルコニウム基合金基体か
ら成る部材に酸素拡散層１０を形成した。第３図
には一種類の形状の端栓の例を示してあるが、他
の形状の端栓についても同様のものが得られる。
この本発明による酸素拡散層付端栓と、従来の酸
素拡散層を有しない端栓の２種を試験片として前
述のノジユラーコロージヨン加速試験を行い、耐
食性を評価した。即ち500℃107Kg／cm2の水蒸気雰
囲気に保持した後、試験片表面の状態変化、試験
片の腐食による重量変化（腐食増量）、水素含有
量変化、および内部組織の観察などを行つた。 Zircaloy-2 ingots as starting material
A rod material is manufactured in accordance with ASTM standard B351-79, and after cutting the rod material into an end plug shape, oxygen diffusion treatment is performed to create a zirconium-based material as shown in the side view in Figure 3. An oxygen diffusion layer 10 was formed on a member made of an alloy base. Although FIG. 3 shows an example of an end plug having one type of shape, similar end plugs can be obtained with other shapes.
Two types of end plugs, the end plug with an oxygen diffusion layer according to the present invention and the conventional end plug without an oxygen diffusion layer, were used as test pieces to perform the above-mentioned accelerated nodular corrosion test to evaluate their corrosion resistance. That is, after maintaining the test piece in a steam atmosphere of 107 Kg/cm 2 at 500° C., changes in the condition of the test piece surface, weight change due to corrosion of the test piece (corrosion increase), change in hydrogen content, and internal structure were observed.
上記試験において、従来の端栓では、保持時間
数時間経過で表面に斑点状の白色生成物が発生し
時間とともに次第に大きく成長した。腐食増量も
第４図に曲線ａで示す如くであつた。しかし、本
発明に係る酸素拡散層付端栓では、保持時間40時
間後においてもその表面には白色生成物の発生は
全く認められず腐食増量も第４図に曲線ｂで示す
如くほとんど増量せずノジユラーコロージヨンに
対する優れた耐食性を備えていることが確認され
た。さらに、第５図にノジユラーコロージヨン性
に関する水素含有量を示す。なお、水素含有量の
分析は、試験片表面の酸化生成物を除去した後分
析に供した。従来端栓では第５図曲線ａに示すよ
うに水素含有量は増加しており、保持時間40時間
後の内部組織には水素化物ZrHxに帰属される物
質がほぼ均一に分布していた。また、酸素拡散層
付端栓では、第５図曲線ｂに示すようにほとんど
増量が認められず、また内部組織においても水素
化物ZrHxに帰属される物質の量も著しく少量で
あつた。さらに加えて、機械的諸特性について
は、本発明のものが0.2％、耐力が385〜395MPa、
引張強さが549〜553MRa、伸びが31〜32％とな
つており、酸素拡散層を有しない従来のジルコニ
ウム基合金が0.2％、耐力が376MPa、引張強さが
530MPa、伸びが33％であるものと比べて、概ね
同等かそれ以上であることが確認された。 In the above test, with the conventional end plug, speckled white products were generated on the surface after several hours of holding time and gradually grew larger with time. The corrosion weight increase was also as shown by curve a in FIG. However, with the end plug with an oxygen diffusion layer according to the present invention, no white products were observed on the surface even after a holding time of 40 hours, and the amount of corrosion hardly increased as shown by curve b in Figure 4. It was confirmed that it has excellent corrosion resistance against natural corrosion. Further, FIG. 5 shows the hydrogen content related to nodular corrosion properties. Note that the hydrogen content was analyzed after removing oxidation products from the surface of the test piece. In the conventional end plug, the hydrogen content increased as shown by curve a in Figure 5, and the substance belonging to the hydride ZrHx was almost uniformly distributed in the internal structure after 40 hours of holding time. Furthermore, in the case of the end plug with an oxygen diffusion layer, almost no increase was observed as shown in curve b in Figure 5, and the amount of substances belonging to the hydride ZrHx was also extremely small in the internal structure. In addition, the mechanical properties of the present invention are 0.2%, the yield strength is 385-395MPa,
The tensile strength is 549 to 553 MRa and the elongation is 31 to 32%, compared to the conventional zirconium-based alloy without an oxygen diffusion layer, which has a yield strength of 376 MPa and a tensile strength of 0.2%.
It was confirmed that the elongation is roughly the same or higher than that of 530MPa and 33% elongation.
なお、本発明に用いる端栓のジルコニウム基合
金としては例えばジルコニウムに重量比で錫を
1.2〜1.7％、鉄を0.07〜0.20％、クロムを0.05〜
0.15％、ニツケルを0.03〜0.08％添加して成るジ
ルカロイ−２と呼称されるものが使用されてい
る。 The zirconium-based alloy for the end plug used in the present invention may include, for example, a weight ratio of tin to zirconium.
1.2~1.7%, iron 0.07~0.20%, chromium 0.05~
Zircaloy-2, which contains 0.15% of nickel and 0.03 to 0.08% of nickel, is used.
また上記組成のジルコニウム基合金を500〜
1000℃の電気炉内で、１×10-3KmHg〜１×104Km
Hgの酸素分圧の雰囲気に１秒〜１時間で加熱処
理することにより表面または表面近傍に酸素拡散
層が形成されて成るジルコニウム基合金基体が得
られる。この製造方法乃至処理方法において、温
度は500〜1000℃にする事が好ましく、500℃以下
では所要の酸素拡散層が形成し難く、また1000℃
を超えると合金構造において粒径の粗大化などに
より機械的強度の低下を招来する傾向が認められ
るためである。また、時間は１秒〜１時間にする
事が好ましく１秒以下では所要の酸素拡散層の形
成が充分でなく、また１時間を超えると酸素拡散
層が厚くなりすぎ、合金の延性の低下を招来する
ことが認められるためである。さらに、雰囲気に
つき酸素分圧を１×10-3KmHgから１×104KmHg
の範囲としたのはこの範囲外では所要の酸素拡散
層を形成し難たかつたり、或いは経済的にかえつ
て不利だつたりするからである。 In addition, zirconium-based alloys with the above composition are
In an electric furnace at 1000℃, 1×10 -3 KmHg to 1×10 4 Km
A zirconium-based alloy substrate with an oxygen diffusion layer formed on or near the surface can be obtained by heat treatment in an atmosphere with an oxygen partial pressure of Hg for 1 second to 1 hour. In this manufacturing method or treatment method, the temperature is preferably 500 to 1000°C; below 500°C it is difficult to form the required oxygen diffusion layer;
This is because if it exceeds 100%, there is a tendency for the alloy structure to have a decrease in mechanical strength due to coarsening of the grain size, etc. In addition, it is preferable that the time is between 1 second and 1 hour, and if it is less than 1 second, the required oxygen diffusion layer will not be formed sufficiently, and if it exceeds 1 hour, the oxygen diffusion layer will become too thick, which may reduce the ductility of the alloy. This is because they are allowed to invite guests. Furthermore, the oxygen partial pressure per atmosphere is changed from 1×10 -3 KmHg to 1×10 4 KmHg.
The reason why this range is set is that outside this range, it may be difficult to form the required oxygen diffusion layer, or it may even be economically disadvantageous.
また、ジルカロイ−２のインゴツトを原料とし
て、ASTM規格B351−79に従つて製造したロツ
ド材に切削加工等を施して端栓形状に加工する方
法が一般的である。得られた端栓は核燃料ペレツ
トを納めた被覆管の両端に溶接される。 Further, it is common to use a Zircaloy-2 ingot as a raw material and process a rod material manufactured in accordance with ASTM standard B351-79 into an end plug shape by cutting or the like. The resulting end plugs are welded to both ends of the cladding tube containing the nuclear fuel pellets.
本発明に係る酸素拡散処理は、上記の製造工程
のうちどの工程で施工してもよいが、特に端栓形
状のジルカロイ−２材料について行うことが望ま
しい。このような酸素拡散処理を行うと、その
後、端栓を被覆管に溶接した後でも形成された酸
素拡散層がそのまま残存して所要の耐ノジユラー
コロージヨン性および機械的特性を長期にわたつ
て発揮する。 The oxygen diffusion treatment according to the present invention may be performed at any of the above manufacturing steps, but it is particularly desirable to perform the oxygen diffusion treatment on the end plug-shaped Zircaloy-2 material. When such oxygen diffusion treatment is performed, the oxygen diffusion layer formed remains intact even after the end plug is welded to the cladding tube, and the required nodular corrosion resistance and mechanical properties are maintained over a long period of time. Demonstrate.
なお本発明に係る端栓の製造方法としては誘導
加熱炉や赤外線炉による加熱方法を用いてもよ
い。また合金の表面層のみを500〜1000℃に保つ
だけでも充分であるから、レーザービームや電子
ビームによる加熱方法でも所要の酸素拡散層が形
成される。 Note that as a method for manufacturing the end plug according to the present invention, a heating method using an induction heating furnace or an infrared furnace may be used. Furthermore, since it is sufficient to maintain only the surface layer of the alloy at 500 to 1000°C, the required oxygen diffusion layer can also be formed by a heating method using a laser beam or an electron beam.
なお上記実施例に用いたノジユラーコロージヨ
ン試験とは試験片を500℃、107Kg／cm2の水蒸気環
境中に保持するもので、この試験環境は実炉環境
すなわち289℃、71Kg／cm2の沸騰水雰囲気で且つ
中性子照射の影響を考慮したものである。 The nodular corrosion test used in the above examples is one in which the test piece is held in a steam environment of 500℃ and 107Kg/ cm2 , and this test environment is similar to the actual furnace environment, that is, 289℃ and 71Kg/ cm2 . This is a boiling water atmosphere and takes into account the effects of neutron irradiation.
なお上記実施例ではジルカロイ−２を用いた場
合を示したが他にジルカロイ−４、Zr−2.5％Nb
系、Zr−１％系及びオーゼナイトなどのジルコ
ニウム基合金基体を端栓材料として用いる場合に
おいても酸素拡散層を形成することにより上記実
施例同様の作用効果を得ることができる。 In the above example, Zircaloy-2 was used, but Zircaloy-4, Zr-2.5%Nb
Even when a zirconium-based alloy substrate such as Zr-based, Zr-1% based, or Auzenite is used as the end plug material, the same effects as in the above embodiment can be obtained by forming an oxygen diffusion layer.
また、端栓は一般にオートクレーブ処理を施さ
ないが、オートクレーブ処理をかなり長時間施す
ことによつても酸素拡散層が形成され、実施例同
様の効果を達成できる。更に通常のオートクレー
ブ処理により形成された表面の酸化物層を、内部
に拡散して酸素拡散層を形成させても良い。 Further, although the end plug is generally not subjected to autoclave treatment, an oxygen diffusion layer is formed even if autoclave treatment is performed for a considerably long period of time, and the same effect as that of the example can be achieved. Furthermore, an oxide layer on the surface formed by ordinary autoclave treatment may be diffused into the interior to form an oxygen diffusion layer.
なお酸素拡散処理の後に急冷処理を施すと該酸
素拡散処理は、より一層の効果がある。 Note that if a rapid cooling treatment is performed after the oxygen diffusion treatment, the oxygen diffusion treatment is even more effective.
以上の結果から明らかなように本発明に係る少
なくも表面に設けられた酸素拡散層を有するジル
コニウム基合金からなる端栓はノジユラーコロー
ジヨンに対するすぐれた耐食性および機械的特性
を備えている。
As is clear from the above results, the end plug made of a zirconium-based alloy having an oxygen diffusion layer provided at least on its surface according to the present invention has excellent corrosion resistance and mechanical properties against nodular corrosion.
またジルコニウム基合金は酸素を多く含有する
ほど硬さが増加する。そのため、耐摩耗性が向上
し、端栓とタイプレートに穿孔された支持孔との
摺動摩耗による肉減りのおそれもない。 In addition, the harder the zirconium-based alloy contains oxygen, the harder it becomes. Therefore, wear resistance is improved, and there is no fear of thinning due to sliding wear between the end plug and the support hole bored in the tie plate.
かくして本発明の端栓は実炉において使用した
場合も長期間に亘つて所要の機能を果し得ると考
えられる。 Thus, it is believed that the end plug of the present invention can perform the required functions for a long period of time even when used in an actual furnace.
第１図は燃料集合体の一部切欠縦断面図、第２
図は燃料棒の縦断面図、第３図は本発明に係る端
栓の一部切欠側面図、第４図および第５図は本発
明に係る端栓の耐食性特性と従来端栓の耐食性特
性との加速試験の結果を比較して示す曲線図であ
る。
１……上部タイプレート、２……下部タイプレ
ート、３……燃料棒、４……チヤンネルボツク
ス、５……被覆管、６……核燃料ペレツト、７…
…プレナムスプリング、８……上部端栓、９……
下部端栓、１０……酸素拡散層。
Figure 1 is a partially cutaway vertical sectional view of the fuel assembly;
FIG. 3 is a partially cutaway side view of the end plug according to the present invention, and FIGS. 4 and 5 are the corrosion resistance characteristics of the end plug according to the present invention and the corrosion resistance characteristics of the conventional end plug. It is a curve diagram showing a comparison of the results of an accelerated test with . DESCRIPTION OF SYMBOLS 1... Upper tie plate, 2... Lower tie plate, 3... Fuel rod, 4... Channel box, 5... Cladding tube, 6... Nuclear fuel pellet, 7...
...Plenum spring, 8...Top end plug, 9...
Lower end plug, 10...Oxygen diffusion layer.
Claims (1)
おいて、前記ジルコニウム基合金の少なくとも表
面に酸素拡散層を具備したことを特徴とする燃料
棒の端栓。1. An end plug for a fuel rod made of a zirconium-based alloy, characterized in that an oxygen diffusion layer is provided on at least the surface of the zirconium-based alloy.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57099406A JPS58216986A (en) | 1982-06-11 | 1982-06-11 | Fuel rod plug |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57099406A JPS58216986A (en) | 1982-06-11 | 1982-06-11 | Fuel rod plug |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58216986A JPS58216986A (en) | 1983-12-16 |
| JPH0321077B2 true JPH0321077B2 (en) | 1991-03-20 |
Family
ID=14246601
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57099406A Granted JPS58216986A (en) | 1982-06-11 | 1982-06-11 | Fuel rod plug |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58216986A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20160081310A (en) | 2014-12-31 | 2016-07-08 | 한국항공우주산업 주식회사 | Molding apparatus of raw material for aircraft reinforcement |
-
1982
- 1982-06-11 JP JP57099406A patent/JPS58216986A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20160081310A (en) | 2014-12-31 | 2016-07-08 | 한국항공우주산업 주식회사 | Molding apparatus of raw material for aircraft reinforcement |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58216986A (en) | 1983-12-16 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4894203A (en) | Nuclear fuel element having oxidation resistant cladding | |
| US5341407A (en) | Inner liners for fuel cladding having zirconium barriers layers | |
| US4992240A (en) | Alloys based on zirconium having proportional amount of tin, iron, chromium and oxygen | |
| US5519748A (en) | Zircaloy tubing having high resistance to crack propagation | |
| US5247550A (en) | Corrosion resistant zirconium liner for nuclear fuel rod cladding | |
| JPH0790522A (en) | Method for manufacturing zircaloy tube having excellent crack growth resistance | |
| US5434897A (en) | Hydride damage resistant fuel elements | |
| EP0155167A2 (en) | Cladding tubes for containing nuclear fuel material | |
| US5524032A (en) | Nuclear fuel cladding having an alloyed zirconium barrier layer | |
| US6192098B1 (en) | Corrosion and hydride resistant nuclear fuel rod | |
| US20090060115A1 (en) | Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear pressure water reactor | |
| KR100766202B1 (en) | Zirconium alloy and components for the core of light water cooled nuclear reactors | |
| KR100710606B1 (en) | Zirconium alloy excellent in corrosion resistance and hydrogenation resistance to water and water vapor, processing heat transformation method of the alloy and structural material made of the alloy | |
| EP0287875B1 (en) | Zirconium cladded pressurized water reactor nuclear fuel element | |
| JPH0321077B2 (en) | ||
| US4863685A (en) | Corrosion resistant zirconium alloys | |
| US20050265513A1 (en) | Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear boiling water reactor | |
| US4169743A (en) | Zirconium-base alloy nuclear fuel container and method | |
| US20060081313A1 (en) | Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof | |
| Greenfield | A comparison of Magnox A 12 and ZA alloys as canning materials for nuclear reactors | |
| CA1079093A (en) | Zirconium-base alloy nuclear fuel container and method | |
| US5735974A (en) | Irradiated intermetallic compound containing part of light-water reactor | |
| JPS6031089A (en) | Nuclear fuel composite coated pipe and manufacture thereof | |
| JPH0560076B2 (en) | ||
| JPS645661B2 (en) |