JPS6364275B2 - - Google Patents
Info
- Publication number
- JPS6364275B2 JPS6364275B2 JP55050748A JP5074880A JPS6364275B2 JP S6364275 B2 JPS6364275 B2 JP S6364275B2 JP 55050748 A JP55050748 A JP 55050748A JP 5074880 A JP5074880 A JP 5074880A JP S6364275 B2 JPS6364275 B2 JP S6364275B2
- Authority
- JP
- Japan
- Prior art keywords
- billet
- zirconium
- cladding
- composite
- tube
- 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
Links
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 32
- 238000005253 cladding Methods 0.000 claims description 31
- 229910052726 zirconium Inorganic materials 0.000 claims description 31
- 239000002131 composite material Substances 0.000 claims description 26
- 239000000446 fuel Substances 0.000 claims description 16
- 238000000034 method Methods 0.000 claims description 14
- 238000004519 manufacturing process Methods 0.000 claims description 12
- 239000000463 material Substances 0.000 claims description 11
- 239000003758 nuclear fuel Substances 0.000 claims description 11
- 238000003825 pressing Methods 0.000 claims description 4
- 230000004888 barrier function Effects 0.000 description 20
- 229910001093 Zr alloy Inorganic materials 0.000 description 14
- 230000004992 fission Effects 0.000 description 8
- 229910052751 metal Inorganic materials 0.000 description 8
- 239000002184 metal Substances 0.000 description 8
- 238000012545 processing Methods 0.000 description 7
- 229910045601 alloy Inorganic materials 0.000 description 5
- 239000000956 alloy Substances 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 5
- 238000007796 conventional method Methods 0.000 description 4
- 239000002826 coolant Substances 0.000 description 4
- 238000009792 diffusion process Methods 0.000 description 4
- 238000001125 extrusion Methods 0.000 description 4
- 230000007797 corrosion Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 238000001192 hot extrusion Methods 0.000 description 3
- 230000009467 reduction Effects 0.000 description 3
- 229910000881 Cu alloy Inorganic materials 0.000 description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 238000005304 joining Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000000452 restraining effect Effects 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 229910000838 Al alloy Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 238000007792 addition Methods 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 230000004323 axial length Effects 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 238000006757 chemical reactions by type Methods 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 239000000356 contaminant Substances 0.000 description 1
- 238000002788 crimping Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011946 reduction process Methods 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001256 stainless steel alloy Inorganic materials 0.000 description 1
- 230000003746 surface roughness Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 238000003466 welding 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
- Extrusion Of Metal (AREA)
Description
本発明は原子炉燃料要素に係り、特にジルコニ
ウム合金管の内側表面にジルコニウムの金属障壁
を設ける複合被覆型燃料被覆管用複合ビレツトの
新規な製造法に関する。
現在、動力炉用原子炉の核燃料要素は管状の耐
食性、非反応性かつ良熱伝導性の被覆内に核燃料
物質を封入している。このような燃料要素を一定
間隔に格子状に組立てて燃料集合体を形成し、こ
れら燃料集合体を適当数組合せて自己持続型核分
裂反応の可能な核分裂連鎖反応型集合体又は炉心
を形成する。この炉心を冷却材が通過する原子炉
容器内に入れる。
被覆はいくつかの目的で使用され、その2つの
主要目的のうちの第1は、核燃料と冷却材、又は
核燃料と減速材との化学反応を防止することにあ
る。第2の目的は、一部が気体である放射性核分
裂生成物が燃料から冷却材又は減速材の中に漏れ
出るのを防止することにある。普通用いられてい
る被覆材料は、ステンレス鋼及びジルコニウム合
金である。
被覆材としてある種の金属及び合金を使用して
核燃料要素を製造及び運転する場合、特定の条件
下でこれらの被覆材料に機械的又は化学的反応が
生ずることから種々の問題が起つている。ジルコ
ニウム及びその合金は、定常条件下では優秀な核
燃料被覆材である。その理由は、ジルコニウム及
びその合金は、中性子吸収断面積が小さく、さら
に約400℃以下の温度では、原子炉冷却材及び減
速材として普通に使用される純水又は水蒸気の存
在下で強く、延性を有し、極めて安定で、かつ非
反応性であるためである。
しかし、燃料要素の挙動として、核燃料、被覆
及び核分裂反応中に生成する核分裂生成物間の相
互作用により被覆材が脆くなり、割れが生じる可
能性があるという問題がある。この望ましくない
挙動は、さらに燃料と被覆との熱膨張差に基づく
燃料被覆の局部的な機械的応力によつて促進され
ることが確かめられた。原子炉の運転中に分裂反
応によつて、核分裂生成物が核燃料から放出さ
れ、被覆材表面に存在する。ヨウ素やカドミウム
などの特定核分裂生成物の存在下では、局部応力
及びひずみの作用により、応力腐食割れが生じ
る。
かゝる障害を防止する方策として、燃料と被覆
との間に各種の金属障壁を設けることが試みられ
ている。これらの中で金属障壁として、適度な純
度のジルコニウム合金管の内側面に金属結合させ
た複合型被覆管が最も有望視されている。ジルコ
ニウム障壁の厚さは被覆管厚さの約5〜30%であ
る。ジルコニウムはジルコニウム合金に比べて、
照射中軟さを維持するので、核燃料要素内の局部
ひずみを減じ、応力腐食割れから被覆管を保護す
る。また重大な中性子捕獲ペナルテイ、熱伝達ペ
ナルテイ又は材料の非両立問題を惹起しない点も
優れた特徴である。
かかる複合型被覆管は通常次のような方法によ
つて製造される。第1図に示すように、金属障壁
となるジルコニウムインゴツトと被覆材となるジ
ルコニウム合金インゴツトを溶製し、ジルコニウ
ム中空ビレツトをジルコニウム合金中空ビレツト
中に挿入し、一体化して複合ビレツトとする。こ
の複合ビレツトを通常の熱間押出法により約500
〜750℃の高温で押出す。次に押出複合管に通常
の管縮小加工を施して所望の寸法の被覆管を完成
する。
このような複合型被覆管は、ジルコニウム障壁
の厚さが所望の寸法に制御されていることゝ、ジ
ルコニウム障壁と被覆材とが全面にわたつて完全
に金属結合していることが極めて重要である。そ
のためには、複合ビレツトの状態でジルコニウム
中空ビレツト(内筒)とジルコニウム合金中空ビ
レツト(外筒)とが一体化しており、以降の押出
及び管縮小加工時に一体の状態で変形されること
が必要である。このような一体化をするため従来
のような方法がとられている。
(1) 内筒を外筒に挿入し、爆発接合によつて一体
化する。
(2) 内筒を外筒に挿入し、加熱して拡散接合させ
て一体化する。
しかし、以上の従来法は、対象が燃料被覆管と
いう非常に高い信頼性を要するもので、なお次の
ような欠点を有する。すなわち、(1)の方法は内径
が小さなもの(約φ30mm以下)には適用できな
い。また外筒と内筒の接合が軸方向に均一でな
い。接合界面はさざ波状になる等の問題がある。
(2)の方法は長時間の高温加熱(例えば750℃×8
時間)が必要で、しかも均一な拡散が生ずるよう
に加熱中に圧力をかけるとか、予め機械的に予備
結合をする必要があるなど工程が複数で条件の管
理が困難である。また真空又は不活性雰囲気など
を用いないと接合界面が酸化し、以降の熱間押
出、管縮小加工に支障をきたす。
以上のことから、ジルコニウム障壁が全面に亘
つて均一で良好な結合を達成するためには、複合
ビレツトの一体化方法が製法上きわめて重要な工
程である。
本発明の目的は、金属障壁であるジルコニウム
内筒と被覆材であるジルコニウム合金外筒を一体
化して良好な燃料被覆管用複合ビレツトの製法を
提供するにある。
本発明は、ジルコニウム内筒ビレツトをジルコ
ニウム合金外筒ビレツトに機械的に結合する方法
に関するものである。すなわち、ジルコニウム内
筒ビレツトをジルコニウム合金外筒ビレツトに挿
入した後、内筒ビレツト内部に弾性体を挿入し、
次に該圧力媒体を外部より軸方向に圧縮荷重を加
えることにより、内筒を半径方向に拡げ外筒ビレ
ツト内面に圧着させるもである。本発明において
は、圧力媒体をゴム等の弾性体とすることによ
り、圧力媒体が流体と同じ挙動をするので、円周
方向及び軸方向全面に亘つて均一な力を内筒に作
用することができ、また力の制御が容易で、ジル
コニウム内筒の肉厚変形なしに、十分信頼性の高
い機械的結合が達成できる。
上記のゴム等による拡管法はすでにアルミニウ
ムや銅合金等の二重管製法として公知であるが、
燃料被覆管用複合ビレツトの製造にあつては、次
の点を考慮すべきである。
拡管時の荷重は次式によつて求める。
W=PAr/η ……(1)
ここで、W:拡管荷重(Kg)
P:拡管圧力(Kg/mm2)
Ar:拡管用ゴムの断面積(mm2)
η:拡管効率(0.85〜0.9)
上式を用いて、ジルコニウム内筒の拡管圧力を
変えて引抜固着力を測定した結果を第2図に示
す。拡管圧力が大きくなるほど引抜固着力も増大
する。なお、引抜固着力とは、拡管後、内筒を引
抜に要する荷重である。一般には、アルミニウム
や銅合金の二重管の引抜固着力は同図斜線1に示
すように100〜1000Kgの範囲内で十分である。し
かし、燃料被覆管を製造するためには、得られた
複合ビレツトを熱間押出及び管縮小加工により加
工率80%以上の加工を施すので、一般の場合より
も引抜固着力を高めておく必要がある。本発明者
等は、引抜固着力の下限値について種々実験した
結果、同図斜線部2に示すように固着力は従来の
2倍以上が必要であることを見い出した。
次にジルコニウム障壁厚さを目標値に制御する
ためには拡管時のジルコニウム内筒とジルコニウ
ム合金外筒の肉厚比が極めて重要であることを見
い出した。肉厚比は下式で表わされる。
t=Zr/Zry+Zr×100(%) ……(2)
ここでt:肉厚比
Zr:ジルコニウム内筒の肉厚
Zry:ジルコニウム合金外筒の肉厚
ジルコニウム内筒とジルコニウム合金外筒の肉
厚比を種々変えて拡管し、最終的に複合型被覆管
を製作し、最終段階での肉厚比を求めた。その結
果、拡管時の肉厚比よりも最終段階の肉厚比が5
〜10%小さくなることがわかつた。これはジルコ
ニウムのほうがジルコニウム合金よりも加工され
やすいことによる。したがつて、所望のジルコニ
ウム障壁の厚さを得るためには、拡管時の肉厚比
をあらかじめ5〜10%高めにしておく方がよい。
以上の特徴により、従来法よりジルコニウム障
壁厚さのばらつきが小さく、かつ全面に亘つて均
一な圧着状態を有する複合被覆型燃料被覆管の製
造ができる。
本発明を具体的に示すために、以下に実施例を
述べる。
外筒ビレツトはASTMB353、グレードRA―
1に適合する標準ジルカロイ―2合金をアーク溶
解により溶製した。金属障壁となる内筒ビレツト
用素材としては、ジルコニウムをアーク溶解し、
純ジルコニウムを溶製した。
両インゴツトを熱間鍛造し、本発明のゴム拡管
を施すために、それぞれ中空ビレツトに切削加工
した。中空の内筒ビレツトの外表面及び外筒ビレ
ツトの内表面を平均表面粗さが10μm以下、特に
6μm以下になるように研磨し、平滑にする。その
理由は、金属障壁の長さ方向の厚さが最終製品で
ある複合被覆管でできるだけ一様になるようにす
るためである。ゴム拡管用中空ビレツトの寸法及
びそれらの肉厚比を第1表に示す。実施例1及び
2は、ジルコニウム障壁厚さを75±5μm、実施例
3及び4は、80±5μmを目標としたものである。
なお、内筒ビレツトの突出量は、実施例1及び2
では0.5mm、実施例3及び4では3mmであつた。
The present invention relates to nuclear reactor fuel elements, and more particularly to a novel method for manufacturing a composite billet for a composite clad fuel cladding tube in which a zirconium metal barrier is provided on the inner surface of the zirconium alloy tube. Currently, nuclear fuel elements for power reactors encapsulate nuclear fuel material within a tubular, corrosion-resistant, non-reactive, and thermally conductive cladding. Such fuel elements are assembled in a lattice shape at regular intervals to form a fuel assembly, and an appropriate number of these fuel assemblies are combined to form a nuclear fission chain reaction type assembly or reactor core capable of self-sustaining nuclear fission reactions. This core is placed in a reactor vessel through which coolant passes. Coatings are used for several purposes, the first of which is to prevent chemical reactions between the nuclear fuel and the coolant or between the nuclear fuel and the moderator. A second purpose is to prevent radioactive fission products, which are partially gaseous, from escaping from the fuel into the coolant or moderator. Commonly used coating materials are stainless steel and zirconium alloys. Various problems arise in the manufacture and operation of nuclear fuel elements using certain metals and alloys as cladding materials due to mechanical or chemical reactions that occur in these cladding materials under certain conditions. Zirconium and its alloys are excellent nuclear fuel cladding materials under steady-state conditions. The reason is that zirconium and its alloys have a small neutron absorption cross section, and at temperatures below about 400°C, they are strong and ductile in the presence of pure water or steam, commonly used as reactor coolants and moderators. This is because it is extremely stable and non-reactive. However, the behavior of the fuel element is problematic in that interactions between the nuclear fuel, the cladding, and the fission products produced during the fission reaction can cause the cladding to become brittle and crack. It has been determined that this undesirable behavior is further exacerbated by local mechanical stresses in the fuel cladding due to differential thermal expansion between the fuel and the cladding. During operation of a nuclear reactor, fission products are released from the nuclear fuel by fission reactions and are present on the surface of the cladding. In the presence of certain fission products such as iodine and cadmium, stress corrosion cracking occurs due to the action of local stress and strain. As a measure to prevent such damage, attempts have been made to provide various metal barriers between the fuel and the cladding. Among these, a composite cladding tube made of a zirconium alloy tube of moderate purity and metallurgically bonded to the inner surface is considered the most promising as a metal barrier. The thickness of the zirconium barrier is about 5-30% of the cladding thickness. Compared to zirconium alloys, zirconium
It remains soft during irradiation, reducing local strains within the nuclear fuel element and protecting the cladding from stress corrosion cracking. Another advantageous feature is that it does not cause significant neutron capture penalties, heat transfer penalties, or material incompatibility problems. Such a composite cladding tube is usually manufactured by the following method. As shown in FIG. 1, a zirconium ingot serving as a metal barrier and a zirconium alloy ingot serving as a covering material are melted, a zirconium hollow billet is inserted into a zirconium alloy hollow billet, and they are integrated to form a composite billet. Approximately 500 pieces of this composite billet are produced using the normal hot extrusion method.
Extrusion at high temperature ~750℃. Next, the extruded composite tube is subjected to a conventional tube reduction process to complete a cladding tube of desired dimensions. For such composite cladding, it is extremely important that the thickness of the zirconium barrier is controlled to the desired dimensions, and that the zirconium barrier and the cladding material have a complete metallic bond over the entire surface. . To do this, the zirconium hollow billet (inner cylinder) and the zirconium alloy hollow billet (outer cylinder) must be integrated in the composite billet state, and deformed as one body during subsequent extrusion and tube reduction processing. It is. Conventional methods are used to achieve such integration. (1) Insert the inner cylinder into the outer cylinder and integrate them by explosive welding. (2) Insert the inner cylinder into the outer cylinder and heat to diffusion bond and integrate. However, the conventional method described above requires extremely high reliability since the object is a fuel cladding tube, and has the following drawbacks. In other words, method (1) cannot be applied to those with a small inner diameter (approximately φ30 mm or less). Furthermore, the connection between the outer cylinder and the inner cylinder is not uniform in the axial direction. There are problems such as the bonding interface becoming ripple-like.
Method (2) involves long-term high-temperature heating (e.g. 750℃ x 8
Moreover, it is difficult to control the conditions as there are multiple steps, such as applying pressure during heating to ensure uniform diffusion and mechanical pre-bonding in advance. Furthermore, if a vacuum or inert atmosphere is not used, the bonding interface will oxidize, which will interfere with subsequent hot extrusion and tube reduction processing. From the above, in order to achieve uniform and good bonding of the zirconium barrier over the entire surface, the method of integrating the composite billet is an extremely important step in the manufacturing process. An object of the present invention is to provide a method for manufacturing a good composite billet for a fuel cladding tube by integrating a zirconium inner cylinder as a metal barrier and a zirconium alloy outer cylinder as a cladding material. The present invention relates to a method for mechanically bonding a zirconium inner billet to a zirconium alloy outer billet. That is, after inserting the zirconium inner billet into the zirconium alloy outer billet, inserting the elastic body inside the inner billet,
Next, by applying a compressive load to the pressure medium in the axial direction from the outside, the inner cylinder is expanded in the radial direction and is pressed against the inner surface of the outer cylinder billet. In the present invention, by using an elastic body such as rubber as the pressure medium, the pressure medium behaves in the same way as a fluid, so that a uniform force can be applied to the inner cylinder over the entire circumferential direction and axial direction. In addition, the force can be easily controlled, and a sufficiently reliable mechanical connection can be achieved without deforming the wall thickness of the zirconium inner cylinder. The above-mentioned tube expansion method using rubber etc. is already known as the double tube manufacturing method for aluminum, copper alloy, etc.
When manufacturing composite billets for fuel cladding, the following points should be considered. The load during pipe expansion is calculated using the following formula. W=PA r /η...(1) Where, W: Pipe expansion load (Kg) P: Pipe expansion pressure (Kg/mm 2 ) A r : Cross-sectional area of tube expansion rubber (mm 2 ) η: Pipe expansion efficiency (0.85 ~0.9) Figure 2 shows the results of measuring the pull-out fixing force using the above formula and varying the expansion pressure of the zirconium inner cylinder. As the tube expansion pressure increases, the pull-out fixing force also increases. In addition, the pulling-out fixing force is the load required to pull out the inner cylinder after pipe expansion. Generally, the pulling force of a double pipe made of aluminum or copper alloy is sufficient within the range of 100 to 1000 kg, as shown by the diagonal line 1 in the figure. However, in order to manufacture fuel cladding tubes, the resulting composite billet is processed at a processing rate of 80% or more through hot extrusion and tube reduction processing, so it is necessary to have a higher pulling force than in the general case. There is. As a result of various experiments regarding the lower limit value of the pull-out fixing force, the present inventors found that the fixing force should be at least twice that of the conventional one, as shown in the shaded area 2 in the figure. Next, we found that the wall thickness ratio between the zirconium inner tube and the zirconium alloy outer tube during tube expansion is extremely important in order to control the zirconium barrier thickness to the target value. The wall thickness ratio is expressed by the following formula. t = Z r / Z ry + Z r × 100 (%) ...(2) where t: Wall thickness ratio Z r : Wall thickness of zirconium inner cylinder Z ry : Wall thickness of zirconium alloy outer cylinder Zirconium inner cylinder and zirconium The alloy outer cylinder was expanded with various wall thickness ratios, a composite cladding tube was finally manufactured, and the wall thickness ratio at the final stage was determined. As a result, the wall thickness ratio at the final stage was 5
It was found that the size was reduced by ~10%. This is because zirconium is easier to process than zirconium alloys. Therefore, in order to obtain the desired thickness of the zirconium barrier, it is better to increase the wall thickness ratio in advance by 5 to 10% during tube expansion. Due to the above characteristics, it is possible to manufacture a composite cladding type fuel cladding tube which has smaller variations in zirconium barrier thickness and has a uniform crimping condition over the entire surface than the conventional method. Examples will be described below to specifically illustrate the present invention. Outer billet is ASTMB353, grade RA-
A standard Zircaloy-2 alloy conforming to No. 1 was melted by arc melting. The material for the inner cylinder billet, which acts as a metal barrier, is arc-melted zirconium.
Pure zirconium was produced. Both ingots were hot forged and each was cut into a hollow billet in order to perform the rubber tube expansion of the present invention. The outer surface of the hollow inner billet and the inner surface of the outer billet have an average surface roughness of 10μm or less, especially
Polish and smooth to a thickness of 6 μm or less. The reason for this is to ensure that the longitudinal thickness of the metal barrier is as uniform as possible in the final composite cladding. Table 1 shows the dimensions of the hollow billet for rubber tube expansion and their wall thickness ratios. Examples 1 and 2 aim for a zirconium barrier thickness of 75±5 μm, and Examples 3 and 4 aim for a zirconium barrier thickness of 80±5 μm.
Note that the protrusion amount of the inner cylinder billet is the same as in Examples 1 and 2.
In Examples 3 and 4, it was 0.5 mm, and in Examples 3 and 4, it was 3 mm.
【表】
第3図は組立てた複合ビレツトを示したもので
ある。この複合ビレツトを機械的に結合し一体化
する本発明の方法を第4図に示す。第4図におい
て左半分は加工前、右半分は加工後を示してい
る。装置はナツト16により支持部材13を介し
て台板14,15を固定しており、複合ビレツト
の拘束型31とビレツト内部に挿入された圧力媒
体41と、該圧力媒体41の両端面に配設したシ
ールリング51と、圧力媒体41と軸方向圧縮荷
重を負荷する加圧ロツド61と、該加圧ロツド6
1に連結された油圧シリンダ7及び下側端板11
に固定された押出部材8とから構成されている。
複合ビレツトを拘束型31に締付けることにより
油圧部材8を内筒ビレツト2に押付ける。この状
態で油圧シリンダ7で発生した軸方向荷重で圧力
媒体41を軸方向に圧縮して、内筒ビレツト2を
半径方向に押拡げ、外筒ビレツトと機械的に結合
させる。押拡げ加工の際内筒ビレツトが軸方向に
縮んだ量だけ端板11に締付ボルト12及び座金
9でとりつけたバネ10の復元力によつて押圧部
材8を軸方向に移動させ、圧力媒体41がすき間
より塑性流動することを防止している。本実施例
では内筒ビレツトを端面まで均一に結合させるた
め、圧力媒体41の軸方向長さをビレツト長より
長くしている。
以上に述べた装置により実施例1〜4とも圧力
3000Kg/cm2にて結合させた。内筒ビレツトの肉厚
の不均一変形はまつたく測定されなかつた。
最終仕上り管の寸法及びジルコニウム障壁厚さ
の測定結果を第2表に示す。ジルコニウム障壁厚
さは、全長にわたつて目標値を満足した。また超
音波試験及び断面観察からジルコニウム障壁とジ
ルカロイ被覆管とは全長に亘つて欠陥がなく良好
な金属結合が達せられていた。[Table] Figure 3 shows the assembled composite billet. The method of the present invention for mechanically joining and integrating this composite billet is shown in FIG. In FIG. 4, the left half shows the state before processing, and the right half shows the state after processing. The device fixes base plates 14 and 15 via a support member 13 with a nut 16, and includes a restraining mold 31 of a composite billet, a pressure medium 41 inserted into the billet, and a pressure medium 41 disposed on both end surfaces of the pressure medium 41. a pressurizing rod 61 that loads the pressure medium 41 and an axial compressive load, and the pressurizing rod 6.
Hydraulic cylinder 7 and lower end plate 11 connected to 1
The extrusion member 8 is fixed to the extrusion member 8.
By tightening the composite billet to the restraining mold 31, the hydraulic member 8 is pressed against the inner cylinder billet 2. In this state, the pressure medium 41 is compressed in the axial direction by the axial load generated by the hydraulic cylinder 7, and the inner billet 2 is expanded in the radial direction and mechanically connected to the outer billet. During the expansion process, the pressing member 8 is moved in the axial direction by the restoring force of the spring 10 attached to the end plate 11 by the tightening bolt 12 and washer 9 by the amount that the inner cylinder billet has shrunk in the axial direction, and the pressure medium 41 is prevented from plastically flowing through the gap. In this embodiment, in order to uniformly connect the inner cylinder billet to the end face, the axial length of the pressure medium 41 is made longer than the billet length. The above-mentioned apparatus was used to reduce pressure in Examples 1 to 4.
Bonding was carried out at 3000Kg/cm 2 . Non-uniform deformation of the wall thickness of the inner cylinder billet was not clearly measured. The measurements of the final finished tube dimensions and zirconium barrier thickness are shown in Table 2. The zirconium barrier thickness satisfied the target value over the entire length. Furthermore, ultrasonic tests and cross-sectional observations revealed that the zirconium barrier and the Zircaloy cladding tube had no defects over the entire length, and a good metallurgical bond had been achieved.
【表】
以上の実施例から明らかなごとく本発明により
以下の効果がある。(1)複合ビレツトの寸法制御が
容易なので金属障壁の厚さを精度高く制御でき
る。(2)複合ビレツトの内径が小さくても適用でき
る。(3)従来法に比し加工時間が短く、作業条件の
管理が容易である。
本発明による複合ビレツトの内筒及び外筒ビレ
ツト間の健全性を高めるため、両者の接合作業を
真空中又は不活性ガス中で実施し、両者間に存在
する微小隙間内の空気、水分又か汚染物を除去
し、又は不活性ガスと置換するのがよい。
本発明は上記実施例に限られるものではなく、
種々の変形や公知技術の付加がなしうる。例え
ば、複合ビレツトを製造する際に、ビレツトを加
熱し、拡散を起させれば、ビレツト同志の結合力
も高まり、従つて加圧力も小さくてもよくなる。
拡散条件は従来公知のものでよい。[Table] As is clear from the above examples, the present invention has the following effects. (1) Since the dimensions of the composite billet are easy to control, the thickness of the metal barrier can be controlled with high precision. (2) Applicable even if the inner diameter of the composite billet is small. (3) Processing time is shorter than conventional methods, and work conditions can be easily managed. In order to improve the soundness between the inner cylinder and outer cylinder billet of the composite billet according to the present invention, the joining operation between the two is carried out in a vacuum or in an inert gas, and air, moisture, or Contaminants may be removed or replaced with inert gas. The present invention is not limited to the above embodiments,
Various modifications and additions of known techniques can be made. For example, when manufacturing a composite billet, if the billet is heated to cause diffusion, the bonding strength between the billets will increase, and therefore the pressing force can be reduced.
The diffusion conditions may be those conventionally known.
第1図は従来の複合型燃料被覆管の製造工程
図、第2図は本発明における加圧条件を説明する
図、第3図は内筒ビレツトを外筒ビレツトに挿入
した状態を示す縦断面図、第4図は本発明におい
て用いられる製造装置の縦断面図である。
Figure 1 is a manufacturing process diagram of a conventional composite fuel cladding tube, Figure 2 is a diagram explaining the pressurization conditions in the present invention, and Figure 3 is a vertical cross section showing the state in which the inner billet is inserted into the outer billet. 4 are longitudinal sectional views of the manufacturing apparatus used in the present invention.
Claims (1)
に、外筒ビレツトよりわずかに長いジルコニウム
の中空内筒ビレツトを挿入し、該内筒ビレツト内
に弾性体を挿入した後、弾性体にビレツトの軸方
向から圧力をかけて、上記外筒ビレツトの内面に
上記内筒ビレツトの外面を密着させることを特徴
とする燃料被覆管用複合ビレツトの製法。1 Insert a hollow inner billet made of zirconium that is slightly longer than the outer billet into a hollow outer billet made of nuclear fuel cladding material, insert an elastic body into the inner billet, and then insert the elastic body in the axial direction of the billet. A method for manufacturing a composite billet for a fuel cladding tube, characterized in that the outer surface of the inner billet is brought into close contact with the inner surface of the outer billet by applying pressure.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5074880A JPS56148486A (en) | 1980-04-15 | 1980-04-15 | Manufacture of composite billet for fuel cladding tube |
| FR8107485A FR2480483B1 (en) | 1980-04-15 | 1981-04-14 | PROCESS FOR PRODUCING A COMPOSITE LINGOT FOR THE MANUFACTURE OF SHEATHING TUBES FOR NUCLEAR FUEL ELEMENTS |
| US06/254,297 US4478363A (en) | 1980-04-15 | 1981-04-15 | Method of production of composite billet for fuel cladding tube |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5074880A JPS56148486A (en) | 1980-04-15 | 1980-04-15 | Manufacture of composite billet for fuel cladding tube |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56148486A JPS56148486A (en) | 1981-11-17 |
| JPS6364275B2 true JPS6364275B2 (en) | 1988-12-12 |
Family
ID=12867448
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5074880A Granted JPS56148486A (en) | 1980-04-15 | 1980-04-15 | Manufacture of composite billet for fuel cladding tube |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56148486A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60129468A (en) * | 1983-12-16 | 1985-07-10 | Toshiba Mach Co Ltd | Manufacture of cylinder |
| US7922065B2 (en) * | 2004-08-02 | 2011-04-12 | Ati Properties, Inc. | Corrosion resistant fluid conducting parts, methods of making corrosion resistant fluid conducting parts and equipment and parts replacement methods utilizing corrosion resistant fluid conducting parts |
| US10118259B1 (en) | 2012-12-11 | 2018-11-06 | Ati Properties Llc | Corrosion resistant bimetallic tube manufactured by a two-step process |
-
1980
- 1980-04-15 JP JP5074880A patent/JPS56148486A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56148486A (en) | 1981-11-17 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP3143015B2 (en) | Improved lining for fuel cladding with zirconium barrier layer | |
| US5517540A (en) | Two-step process for bonding the elements of a three-layer cladding tube | |
| US4372817A (en) | Nuclear fuel element | |
| US4045288A (en) | Nuclear fuel element | |
| US5383228A (en) | Method for making fuel cladding having zirconium barrier layers and inner liners | |
| EP0622470B1 (en) | Method of fabricating zircaloy tubing having high resistance to crack propagation | |
| US4200492A (en) | Nuclear fuel element | |
| EP0624882B1 (en) | Zircaloy tubing having high resistance to crack propagation | |
| US4406012A (en) | Nuclear fuel elements having a composite cladding | |
| EP0047082B1 (en) | Method of production of cladding tube for nuclear fuel element | |
| US5524032A (en) | Nuclear fuel cladding having an alloyed zirconium barrier layer | |
| JPH07287087A (en) | Cladding tube and fuel element | |
| JP2815551B2 (en) | Method of manufacturing cladding | |
| JP2884321B2 (en) | Manufacturing method of dissimilar pipe joint | |
| US5618356A (en) | Method of fabricating zircaloy tubing having high resistance to crack propagation | |
| JPH07301687A (en) | Cladding | |
| US4478363A (en) | Method of production of composite billet for fuel cladding tube | |
| JPS6364275B2 (en) | ||
| EP0151920B1 (en) | Method of processing a control element to be immersed in coolant of a nuclear reactor | |
| JPS6051070B2 (en) | Nuclear fuel elements and their manufacturing methods | |
| Kaufman et al. | Zirconium Cladding of Uranium and Uranium Alloys by Coextrusion | |
| JP2500165B2 (en) | Method for manufacturing fuel cladding tube | |
| JPS60129690A (en) | Nuclear fuel composite coated pipe and manufacture thereof | |
| JPH0260153B2 (en) | ||
| CA1209727A (en) | Buried zirconium layer |