JPH07248391A - Nuclear fuel clad pipe and manufacture thereof - Google Patents
Nuclear fuel clad pipe and manufacture thereofInfo
- Publication number
- JPH07248391A JPH07248391A JP6042388A JP4238894A JPH07248391A JP H07248391 A JPH07248391 A JP H07248391A JP 6042388 A JP6042388 A JP 6042388A JP 4238894 A JP4238894 A JP 4238894A JP H07248391 A JPH07248391 A JP H07248391A
- Authority
- JP
- Japan
- Prior art keywords
- cladding tube
- zirconium
- nuclear fuel
- liner
- oxidation treatment
- 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 18
- 238000004519 manufacturing process Methods 0.000 title claims description 7
- 229910052726 zirconium Inorganic materials 0.000 claims abstract description 39
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims abstract description 38
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 25
- 230000003647 oxidation Effects 0.000 claims abstract description 25
- 238000007254 oxidation reaction Methods 0.000 claims abstract description 25
- 238000011282 treatment Methods 0.000 claims abstract description 24
- 239000001257 hydrogen Substances 0.000 claims abstract description 23
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 23
- 239000000446 fuel Substances 0.000 claims abstract description 19
- 238000005253 cladding Methods 0.000 claims description 78
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 11
- 238000003756 stirring Methods 0.000 claims description 5
- 229910045601 alloy Inorganic materials 0.000 claims description 4
- 239000000956 alloy Substances 0.000 claims description 4
- 230000002093 peripheral effect Effects 0.000 claims description 4
- 239000013078 crystal Substances 0.000 claims description 2
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 claims description 2
- 239000012466 permeate Substances 0.000 claims description 2
- 229910001928 zirconium oxide Inorganic materials 0.000 claims description 2
- 229910001093 Zr alloy Inorganic materials 0.000 abstract description 8
- 230000000452 restraining effect Effects 0.000 abstract 1
- 238000010521 absorption reaction Methods 0.000 description 7
- 239000011248 coating agent Substances 0.000 description 7
- 238000000576 coating method Methods 0.000 description 7
- 239000010410 layer Substances 0.000 description 7
- 239000000463 material Substances 0.000 description 6
- 239000008188 pellet Substances 0.000 description 6
- 239000002826 coolant Substances 0.000 description 4
- 230000035882 stress Effects 0.000 description 4
- 230000007797 corrosion Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 238000005336 cracking Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- 238000004381 surface treatment Methods 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 238000005984 hydrogenation reaction Methods 0.000 description 2
- 238000010301 surface-oxidation reaction Methods 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 102200052313 rs9282831 Human genes 0.000 description 1
- 230000001629 suppression Effects 0.000 description 1
- 239000002344 surface layer Substances 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 150000003754 zirconium Chemical class 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
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は軽水冷却型原子炉の核燃
料要素に使用される核燃料被覆管に関し、特にジルコニ
ウムライナ型被覆管に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear fuel cladding tube used in a nuclear fuel element of a light water cooled nuclear reactor, and more particularly to a zirconium liner type cladding tube.
【０００２】[0002]
【従来の技術】軽水冷却型原子炉に装荷される核燃料要
素は、燃料被覆管内に複数個の核燃料ペレットを積層収
容し、上端部にガス溜用プレナム部と核燃料ペレットを
安定に支持するためのプレナムスプリングを有し、両端
開口部を上部および下部端栓で溶接した構造となってい
る。2. Description of the Related Art A nuclear fuel element loaded in a light water cooled nuclear reactor has a plurality of nuclear fuel pellets stacked and accommodated in a fuel cladding tube and has a top end portion for stably supporting a gas reservoir plenum portion and a nuclear fuel pellet. It has a plenum spring and has a structure in which openings at both ends are welded by upper and lower end plugs.
【０００３】以上の構成において、被覆管には、核燃料
ペレットから放出される放射性核分裂生成物が管外部に
漏洩して冷却材と接触することがないように、安全性の
高い機能が求められている。現在までの運転経験によれ
ば、燃料燃焼度が高くなった段階で出力が急激に上昇す
ると、被覆管と腐食性核分裂生成物との化学反応が起こ
り、また核燃料ペレットが熱膨脹することによって被覆
管に熱応力が加わり、上記両者の重畳作用により被覆管
に応力腐食割れを生ずるおそれのあることが判明した。In the above-mentioned structure, the cladding tube is required to have a highly safe function so that the radioactive fission products emitted from the nuclear fuel pellets will not leak to the outside of the tube and come into contact with the coolant. There is. According to the operation experience to date, when the power rapidly increases at the stage when the fuel burnup becomes high, a chemical reaction between the cladding and corrosive fission products occurs, and the thermal expansion of the nuclear fuel pellets causes thermal expansion of the cladding. It was found that the thermal stress is applied to and the stress corrosion cracking may occur in the cladding tube due to the superposed action of the both.
【０００４】そこで、このような被覆管の応力腐食割れ
を防止するために、被覆管の内周面に例えば厚さ８０〜
１００μｍの純ジルコニウムライナ層が張設された、い
わゆるジルコニウムライナ管が提案されている（特開昭
５５−１６４３９６号公報）。この純ジルコニウムナイ
ナ層によって被覆管と腐食性核分裂生成物との接触が防
止されるとともに、被覆管に発生する局所応力を緩和し
て、当該被覆管の応力腐食割れを防止する効果が期待さ
れている。Therefore, in order to prevent such stress corrosion cracking of the cladding tube, for example, a thickness of 80 to 80 is formed on the inner peripheral surface of the cladding tube.
A so-called zirconium liner tube in which a pure zirconium liner layer having a thickness of 100 μm is stretched has been proposed (JP-A-55-164396). It is expected that this pure zirconium Nina layer will prevent contact between the cladding and corrosive fission products, relax local stress generated in the cladding, and prevent stress corrosion cracking of the cladding. There is.
【０００５】[0005]
【発明が解決しようとする課題】しかし、上記したジル
コニウムライナ層を有する被覆管には、内表面に活性な
純ジルコニウム層が露出しているため、万一何等かの原
因で燃料被覆管の一部が開口して冷却材が燃料要素内に
侵入した場合には、冷却材と燃料ペレットおよびジルコ
ニウムが反応し、その結果燃料要素内の水素濃度が上昇
する。この水素がライナ内表面層を透過して被覆管材料
内に吸収され、被覆管材料の脆化現象を生ずる懸念があ
った。However, since the active pure zirconium layer is exposed on the inner surface of the cladding tube having the above-mentioned zirconium liner layer, the fuel cladding tube may be damaged due to some reason. If the section opens and the coolant penetrates into the fuel element, the coolant reacts with the fuel pellets and zirconium, resulting in an increase in the hydrogen concentration in the fuel element. There is a concern that this hydrogen permeates the inner surface layer of the liner and is absorbed into the cladding material to cause an embrittlement phenomenon of the cladding material.
【０００６】本発明はかかる問題に対処してなされたも
ので、ジルコニウムライナ型被覆管において、燃料被覆
管の一部が破損して被覆管内の水素濃度が上昇した時
に、被覆管材料内に水素が吸収されて被覆管が脆化する
現象を阻止することを目的とする。The present invention has been made to address such a problem, and in a zirconium liner type cladding tube, when a part of the fuel cladding tube is damaged and the hydrogen concentration in the cladding tube rises, hydrogen is contained in the cladding material. The purpose is to prevent the phenomenon that the cladding is absorbed and the cladding tube becomes brittle.
【０００７】[0007]
【課題を解決するための手段】上記目的を達成するため
に、本発明は、燃料要素破損時に被覆管内空間に発生し
た水素ガスが被覆管材料内へ吸収されないようにしたも
のであって、すなわち、内周面にジルコニウムもしくは
ジルコニウムを主成分とする合金から構成されたライナ
を内張りした燃料被覆管において、前記ライナの内表面
または前記ライナの内表面と被覆管外表面に水素透過抑
制機能を有する層が形成されていることを特徴とする。In order to achieve the above object, the present invention is designed so that hydrogen gas generated in a cladding tube inner space at the time of fuel element failure is not absorbed into the cladding tube material, that is, In a fuel cladding tube having an inner peripheral surface lined with zirconium or an alloy containing zirconium as a main component, the inner surface of the liner or the inner surface of the liner and the outer surface of the cladding have a hydrogen permeation suppressing function. It is characterized in that a layer is formed.
【０００８】また、本発明は上記燃料被覆管の製造方法
に関するものであって、内周面にジルコニウムもしくは
ジルコニウムを主成分とする合金から構成されたライナ
を内張りした燃料被覆管の内表面または内外表面を大気
圧下の水蒸気雰囲気中で酸化膜が黒色化するまで酸化処
理することを特徴とする。The present invention also relates to a method for producing the above fuel cladding tube, wherein the inner surface or the inside or outside of the fuel cladding tube is lined with a liner made of zirconium or an alloy containing zirconium as a main component. It is characterized in that the surface is subjected to oxidation treatment in a water vapor atmosphere under atmospheric pressure until the oxide film becomes black.
【０００９】水素透過抑制機能を有する層としては黒色
の単斜晶からなるジルコニウム酸化物が挙げられる。ま
た、上記製造方法で使用する酸化処理装置としては、水
蒸気発生装置を備えかつ水蒸気を攪拌する機能を備えた
酸化処理装置を用いるとよい。Examples of the layer having a hydrogen permeation suppressing function include zirconium oxide composed of black monoclinic crystals. Further, as the oxidation treatment device used in the above-mentioned manufacturing method, it is preferable to use an oxidation treatment device having a steam generator and having a function of stirring steam.
【００１０】[0010]
【作用】ＵＯ2 ペレットを内蔵したジルコニウムライナ
型被覆管が破損し、冷却材が被覆管内に侵入した時の、
被覆管材料への水素の吸収挙動を、種々の内表面処理を
施した被覆管について調べた。[Function] When the zirconium liner type cladding tube containing the UO 2 pellets is damaged and the coolant enters the cladding tube,
The absorption behavior of hydrogen to the cladding material was investigated for the cladding tubes with various inner surface treatments.
【００１１】試験した被覆管は以下の６種である。 表面酸化処理をしていない非ライナ型ジルコニウム合
金製被覆管。 ４２０℃で７２ｋｇ／ｃｍ2 、３時間のオートクレー
ブ処理をして内表面にオートクレーブ膜を形成させた非
ライナ型ジルコニウム合金製被覆管。 ４５０℃で大気圧下、水蒸気中で酸化処理した非ライ
ナ型ジルコニウム合金製被覆管。 表面酸化処理をしていないジルコニウムライナ型ジル
コニウム合金製被覆管。 大気圧の水蒸気中で内表面に白色の酸化物を形成させ
たジルコニウムライナ型ジルコニウム合金製被覆管。 大気圧下、４５０℃で２４時間、水蒸気中で酸化処理
して内表面に黒色の酸化物を形成させたジルコニウムラ
イナ型ジルコニウム合金製被覆管。The following six cladding tubes were tested. Non-liner type zirconium alloy cladding tube without surface oxidation treatment. A non-liner type zirconium alloy cladding tube having an autoclave film formed on the inner surface by autoclaving at 420 ° C. for 72 hours at 72 kg / cm 2 . A non-liner type zirconium alloy cladding tube that has been oxidized in water vapor at 450 ° C. under atmospheric pressure. Zirconium liner type zirconium alloy cladding tube without surface oxidation treatment. A zirconium liner-type zirconium alloy cladding tube having a white oxide formed on its inner surface in atmospheric pressure steam. A zirconium liner-type zirconium alloy cladding tube having an inner surface formed with a black oxide by oxidation treatment in steam at 450 ° C. for 24 hours under atmospheric pressure.
【００１２】上記６種の被覆管を３％の水素を含むアル
ゴンガス雰囲気中に晒し、３５０℃に加熱処理した。所
定時間加熱した後、炉から取り出して、各被覆管の重量
増加を測定し、水素濃度を求めた。約４００時間までの
結果を図３に示す。The above-mentioned 6 kinds of coated tubes were exposed to an argon gas atmosphere containing 3% hydrogen and heat-treated at 350 ° C. After heating for a predetermined time, it was taken out of the furnace and the weight increase of each cladding tube was measured to determine the hydrogen concentration. The results up to about 400 hours are shown in FIG.
【００１３】図３から明らかなように、０．１２％まで
の水素濃度をみると、酸化被膜を形成させていないお
よびは、水素吸収速度が他のものより大きいことがわ
かる。また、酸化被膜を形成させていても、の白色被
膜はおよびと同様に水素吸収速度が大きいことがわ
かる。一方、およびの非ライナ型ジルコニウム合金
製被覆管にそれぞれオートクレーブ膜および酸化膜つけ
たものは、およびの酸化膜のないものより大幅に水
素吸収速度が低下している。ジルコニウムライナ型被覆
管では、の黒色の酸化物を形成させたものだけがお
よびと同様に水素吸収速度が低下している。As is apparent from FIG. 3, when the hydrogen concentration up to 0.12% is observed, it is found that the hydrogen absorption rate is higher than that of the others when the oxide film is not formed. Further, it is found that even if the oxide film is formed, the white film has a high hydrogen absorption rate similarly to and. On the other hand, the non-liner type zirconium alloy cladding tubes with autoclave film and oxide film respectively have significantly lower hydrogen absorption rates than those without and oxide films. In the zirconium liner-type cladding tube, the hydrogen absorption rate was reduced similarly to and only in the case where the black oxide was formed.
【００１４】以上の結果から、ジルコニウムライナ型被
覆管の場合には、ライナ内表面に黒色の酸化被膜を形成
させることにより、水素ガス雰囲気下での水素吸収速度
を低下させ、燃料の破損時における被覆管の脆化を防止
して、より安定性の高い核燃料要素が得られることがわ
かる。From the above results, in the case of a zirconium liner type cladding tube, a black oxide film is formed on the inner surface of the liner to reduce the hydrogen absorption rate in a hydrogen gas atmosphere and to prevent the fuel from being damaged. It can be seen that the embrittlement of the cladding tube is prevented and a more stable nuclear fuel element can be obtained.
【００１５】なお、酸化膜は緻密な場合に黒色となり、
ポーラスな場合に白色となる。これは酸化処理の際の温
度条件や処理時間に依存する。黒色の酸化膜を得るため
には、例えば３００℃以上で５時間以上処理することが
好ましい。When the oxide film is dense, it becomes black,
White when it is porous. This depends on the temperature condition and processing time during the oxidation treatment. In order to obtain a black oxide film, it is preferable to perform treatment at 300 ° C. or higher for 5 hours or longer.
【００１６】[0016]
【実施例】本発明の実施例を図１および図２を参照して
説明する。図１は本発明の実施例のジルコニウムライナ
型被覆管の横断面図である。図中、１はジルカロイ−２
製の核燃料被覆管、２は純ジルコニウムライナ、３はジ
ルコニウムライナ２の内表面に形成された黒色の酸化被
膜、４は被覆管外表面上の酸化被膜である。被覆管１の
外径は１２．２７ｍｍ、肉厚は約０．８ｍｍである。そ
の内表面に酸素濃度８００ｗｔｐｐｍ以下の純ジルコニ
ウム膜２が内張りされている。純ジルコニウム膜２の肉
厚は約９０μｍである。Embodiments of the present invention will be described with reference to FIGS. FIG. 1 is a cross-sectional view of a zirconium liner type cladding tube according to an embodiment of the present invention. In the figure, 1 is Zircaloy-2
Manufactured nuclear fuel cladding tube, 2 is a pure zirconium liner, 3 is a black oxide film formed on the inner surface of the zirconium liner 2, and 4 is an oxide film on the outer surface of the cladding tube. The outer diameter of the cladding tube 1 is 12.27 mm and the wall thickness is about 0.8 mm. A pure zirconium film 2 having an oxygen concentration of 800 wtppm or less is lined on its inner surface. The thickness of the pure zirconium film 2 is about 90 μm.
【００１７】このジルコニウムライナ管（長さ約４００
０ｍｍ）を、図２に示す酸化処理装置で、約４５０℃の
水蒸気に約２０時間晒し、被覆管の内外表面に黒色の酸
化被膜を形成した。This zirconium liner pipe (length about 400
0 mm) was exposed to water vapor at about 450 ° C. for about 20 hours using the oxidation treatment apparatus shown in FIG. 2 to form a black oxide film on the inner and outer surfaces of the cladding tube.
【００１８】この酸化処理装置は、電気炉１１、酸化容
器１２、攪拌装置１３、水蒸気発生器１４、被覆管搬出
入口１５から構成されている。被覆管搬出入口１５から
酸化容器１２内に被覆管１６を搬入し、被覆管全体が４
５０℃になるように電気炉１１を調節し、水蒸気発生器
１４から水蒸気を発生させて酸化容器１２内を水蒸気で
満たす。酸化容器１２には攪拌装置１３が備えてあるの
で、水蒸気は均一に分布される。酸化容器１２の被覆管
搬出入口１５は大気に通じているが、ここから水蒸気が
常に噴出して大気の成分が容器内には逆流しないように
なっている。なお、容器内圧力は大気圧よりわずかに高
いが、第１種圧力容器には該当しない値とした。This oxidation treatment apparatus is composed of an electric furnace 11, an oxidation vessel 12, a stirring device 13, a steam generator 14, and a coating pipe carry-in / out port 15. The coating pipe 16 is carried into the oxidation container 12 from the coating pipe loading / unloading port 15, and the entire coating pipe is 4
The electric furnace 11 is adjusted so as to reach 50 ° C., steam is generated from the steam generator 14, and the inside of the oxidation container 12 is filled with steam. Since the oxidation container 12 is equipped with the stirring device 13, the water vapor is uniformly distributed. The cladding tube carry-in / out port 15 of the oxidation container 12 communicates with the atmosphere, but water vapor is always jetted from here to prevent atmospheric components from flowing back into the container. The pressure in the container was slightly higher than the atmospheric pressure, but the value was not applicable to the type 1 pressure container.
【００１９】酸化処理を施すジルコニウムライナ管は被
覆管搬出入口１５から搬入し、容器内の被覆管移動機構
（図示せず）によって搬出口に移動し、容器より取り出
す。これにより被覆管の酸化処理を連続的に行うことが
可能となる。なお、被覆管の温度および水蒸気中の保持
時間はライナ管内表面上の酸化膜が黒色を保つように最
適化する。The zirconium liner pipe to be subjected to the oxidation treatment is carried in from the coating pipe carrying-in / out port 15, is moved to the carrying-out port by the coating pipe moving mechanism (not shown) in the container, and is taken out from the container. This makes it possible to continuously perform the oxidation treatment of the cladding tube. The temperature of the cladding tube and the holding time in water vapor are optimized so that the oxide film on the inner surface of the liner tube remains black.
【００２０】次に、上記した酸化処理によるジルコニウ
ムライナ管の効果を確認するために、上記した酸化処理
によるジルコニウムライナ管と従来の酸化処理を施して
いないジルコニウムライナ管とを、３００℃で、水素／
水蒸気圧力比を４０に保った雰囲気中で１０時間加熱し
た。この２種類の被覆管を長さ５ｍｍのリング状に切断
し、２８０℃の大気中でリング状試験片の内側から直径
方向に引っ張って、両試料の破断までの伸びの差を比較
した。その結果、本発明の表面処理を加えた被覆管の伸
びは、従来の被覆管の伸びの１．８倍（標準偏差０．
２）であることがわかった。Next, in order to confirm the effect of the zirconium liner pipe by the above-mentioned oxidation treatment, the zirconium liner pipe by the above-mentioned oxidation treatment and the zirconium liner pipe which has not been subjected to the conventional oxidation treatment are heated at 300 ° C. under hydrogen. /
It heated for 10 hours in the atmosphere which kept the water vapor pressure ratio at 40. These two kinds of coated tubes were cut into a ring shape having a length of 5 mm, and the sample was pulled in the diametrical direction from the inside of the ring-shaped test piece in the atmosphere at 280 ° C., and the difference in elongation until breakage of both samples was compared. As a result, the elongation of the cladding tube to which the surface treatment of the present invention has been added is 1.8 times the elongation of the conventional cladding tube (standard deviation 0.
2) was found.
【００２１】これによって本発明の被覆管が従来の被覆
管に比べて水素化に対して抵抗性があり、脆化が抑制さ
れることがわかった。なお、上記実施例ではライナ管内
表面の酸化膜の形成について説明したが、上記酸化処理
装置を使用すれば被覆管外表面も同時に酸化されて同様
に酸化膜が形成される。この外表面に形成された酸化膜
も水素化に対して抵抗性があり、被覆管の脆化抑制に寄
与する。From this, it was found that the cladding tube of the present invention is more resistant to hydrogenation than the conventional cladding tube and the brittleness is suppressed. Although the formation of the oxide film on the inner surface of the liner pipe has been described in the above embodiment, the outer surface of the coating pipe is simultaneously oxidized by the use of the above-mentioned oxidation treatment device, and an oxide film is similarly formed. The oxide film formed on this outer surface is also resistant to hydrogenation and contributes to the suppression of embrittlement of the cladding.
【００２２】[0022]
【発明の効果】以上説明したように、本発明はジルコニ
ウムライナ型被覆管において、燃料被覆管の一部が破損
して被覆管内の水素濃度が上昇した時に、被覆管材料内
に水素が吸収されて被覆管が脆化する現象を阻止するこ
とができ、それによって安定性の高いジルコニウムライ
ナ型被覆管を提供することができる。As described above, according to the present invention, in the zirconium liner type cladding tube, when the fuel cladding tube is partially damaged and the hydrogen concentration in the cladding tube rises, hydrogen is absorbed in the cladding material. It is possible to prevent the embrittlement of the cladding tube, thereby providing a highly stable zirconium liner type cladding tube.
【図１】本発明の一実施例のジルコニウムライナ型被覆
管の横断面図。FIG. 1 is a cross-sectional view of a zirconium liner type cladding tube according to an embodiment of the present invention.
【図２】本発明の燃料被覆管の製造方法に使用される酸
化処理装置の説明図。FIG. 2 is an explanatory view of an oxidation treatment device used in the method for producing a fuel cladding tube of the present invention.
【図３】各種表面処理を施した被覆管の水素吸収量と加
熱時間との関係を示す図。FIG. 3 is a diagram showing a relationship between a hydrogen absorption amount and a heating time of a cladding tube subjected to various surface treatments.
１…ジルカロイ−２製の燃料被覆管、２…純ジルコニウ
ム製ライナ層、３…ジルコニウムライナ表面上の黒色の
酸化被膜、４…被覆管外表面上の黒色の酸化被膜、１１
…電気炉、１２…酸化処理容器、１３…攪拌装置、１４
…水蒸気発生器、１５…被覆管搬出入口、１６…燃料被
覆管。DESCRIPTION OF SYMBOLS 1 ... Fuel cladding tube made of Zircaloy-2, 2 ... Pure zirconium liner layer, 3 ... Black oxide film on zirconium liner surface, 4 ... Black oxide film on outer surface of cladding tube, 11
... electric furnace, 12 ... oxidation treatment container, 13 ... stirring device, 14
... steam generator, 15 ... cladding tube carry-in / out port, 16 ... fuel cladding tube.
───────────────────────────────────────────────────── フロントページの続き (51)Int.Cl.6 識別記号 庁内整理番号 ＦＩ 技術表示箇所 Ｇ２１Ｃ 3/06 ＧＤＬ ─────────────────────────────────────────────────── ─── Continuation of the front page (51) Int.Cl. 6 Identification code Internal reference number FI technical display location G21C 3/06 GDL
Claims (5)
ウムを主成分とする合金から構成されたライナを内張り
した燃料被覆管において、前記ライナの内表面または前
記ライナの内表面と被覆管外表面に水素透過抑制機能を
有する層が形成されていることを特徴とする核燃料被覆
管。1. A fuel cladding tube having an inner peripheral surface lined with zirconium or an alloy containing zirconium as a main component, wherein hydrogen permeates to an inner surface of the liner or an inner surface of the liner and an outer surface of the cladding tube. A nuclear fuel cladding tube having a layer having a suppressing function formed therein.
斜晶からなるジルコニウム酸化物である請求項１記載の
核燃料被覆管。2. The nuclear fuel cladding tube according to claim 1, wherein the layer having a hydrogen permeation suppressing function is zirconium oxide composed of black monoclinic crystals.
ウムを主成分とする合金から構成されたライナを内張り
した燃料被覆管の内表面または内外表面を大気圧下の水
蒸気雰囲気中で酸化膜が黒色化するまで酸化処理するこ
とを特徴とする核燃料被覆管の製造方法。3. An oxide film is blackened on the inner surface or the inner surface of a fuel cladding tube having a liner made of zirconium or an alloy containing zirconium as a main component on its inner peripheral surface in a water vapor atmosphere under atmospheric pressure. A method for producing a nuclear fuel cladding tube, which comprises performing oxidation treatment up to.
発生装置を備えかつ水蒸気を攪拌する機能を備えた酸化
処理容器内で行う請求項３記載の核燃料被覆管の製造方
法。4. The method for producing a nuclear fuel clad pipe according to claim 3, wherein the oxidation treatment in a steam atmosphere is performed in an oxidation treatment container equipped with a steam generator and having a function of stirring the steam.
させた一個または数個の開口部を有しており、該開口部
から核燃料被覆管を搬出入する請求項４記載の核燃料被
覆管の製造方法。5. The nuclear fuel cladding tube according to claim 4, wherein the oxidation treatment container has one or several openings through which water vapor is jetted to the atmosphere side, and the nuclear fuel cladding tube is carried in and out through the openings. Manufacturing method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6042388A JPH07248391A (en) | 1994-03-14 | 1994-03-14 | Nuclear fuel clad pipe and manufacture thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6042388A JPH07248391A (en) | 1994-03-14 | 1994-03-14 | Nuclear fuel clad pipe and manufacture thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH07248391A true JPH07248391A (en) | 1995-09-26 |
Family
ID=12634695
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6042388A Pending JPH07248391A (en) | 1994-03-14 | 1994-03-14 | Nuclear fuel clad pipe and manufacture thereof |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH07248391A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017030775A1 (en) * | 2015-08-14 | 2017-02-23 | Westinghouse Electric Company Llc | Corrosion and wear resistant coating on zirconium alloy cladding |
| CN114752749A (en) * | 2022-04-18 | 2022-07-15 | 西安交通大学 | Method for improving tolerance of cladding material in fast neutron irradiation environment |
-
1994
- 1994-03-14 JP JP6042388A patent/JPH07248391A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017030775A1 (en) * | 2015-08-14 | 2017-02-23 | Westinghouse Electric Company Llc | Corrosion and wear resistant coating on zirconium alloy cladding |
| US9844923B2 (en) | 2015-08-14 | 2017-12-19 | Westinghouse Electric Company Llc | Corrosion and wear resistant coating on zirconium alloy cladding |
| KR20180031052A (en) * | 2015-08-14 | 2018-03-27 | 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 | Corrosion-resistant and abrasion-resistant coatings on zirconium alloy cladding |
| CN108140434A (en) * | 2015-08-14 | 2018-06-08 | 西屋电气有限责任公司 | Corrosion and wear resistance coating on zirconium alloy cladding |
| EP3335220A4 (en) * | 2015-08-14 | 2019-04-17 | Westinghouse Electric Company Llc | CORROSION AND WEAR RESISTANT COATING ON ZIRCONIUM ALLOY SHEATH |
| CN114752749A (en) * | 2022-04-18 | 2022-07-15 | 西安交通大学 | Method for improving tolerance of cladding material in fast neutron irradiation environment |
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