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JPS5833517B2 - nuclear fuel rod - Google Patents
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JPS5833517B2 - nuclear fuel rod - Google Patents

nuclear fuel rod

Info

Publication number
JPS5833517B2
JPS5833517B2 JP54079060A JP7906079A JPS5833517B2 JP S5833517 B2 JPS5833517 B2 JP S5833517B2 JP 54079060 A JP54079060 A JP 54079060A JP 7906079 A JP7906079 A JP 7906079A JP S5833517 B2 JPS5833517 B2 JP S5833517B2
Authority
JP
Japan
Prior art keywords
nuclear fuel
capsule
fuel rod
thin film
tag
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
Application number
JP54079060A
Other languages
Japanese (ja)
Other versions
JPS564094A (en
Inventor
金司 遠藤
孝志 和田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP54079060A priority Critical patent/JPS5833517B2/en
Publication of JPS564094A publication Critical patent/JPS564094A/en
Publication of JPS5833517B2 publication Critical patent/JPS5833517B2/en
Expired legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は被覆管の破損を検知し得るタグガスカプセル入
りの核燃料棒に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fuel rod with a tag gas capsule capable of detecting cladding failure.

一般に原子炉はU−235、U−238またはpu−2
39などの核燃料物質に中性子を照射して核分裂反応を
生じさせ、その除虫ずる熱エネルギーを発電などに利用
している。
Generally reactors are U-235, U-238 or PU-2
Nuclear fuel materials such as No. 39 are irradiated with neutrons to cause a nuclear fission reaction, and the resulting heat energy is used for power generation and other purposes.

現在、多くの原子炉では円柱状のペレット形状をした核
燃料物質を多数個、金属性の被覆管内に密封し、被覆管
の外側に冷却材を循環させることにより核燃料物質から
生ずる熱を炉外に取り出す構造になっている。
Currently, in many nuclear reactors, a large number of nuclear fuel materials in the form of cylindrical pellets are sealed inside a metal cladding tube, and by circulating a coolant outside the cladding tube, the heat generated from the nuclear fuel material is transferred outside the reactor. It has a structure that allows it to be taken out.

核燃料要素は一般にジルカロイまたはステンレス鋼の被
覆管内に二酸化ウランまたはウランとプルトニウムの混
合酸化物のペレットを充填し、被覆管の両端を端栓で閉
塞し溶接してなるもので、上部端栓の近傍にはペレット
の核分裂反応によって生成する核分裂生成ガスを補集し
、かつその生成物の増加による内部圧力の増加を緩和し
かつその圧力増加に伴う要素のクリープ破断寿命の延長
を計るためのプレナム部と、ペレットの各々が輸送中に
その位置が移動しないように軸方向を規制するスプリン
グとから構成されている。
Nuclear fuel elements generally consist of a Zircaloy or stainless steel cladding tube filled with pellets of uranium dioxide or a mixed oxide of uranium and plutonium, and both ends of the cladding tube are closed with end plugs and welded. The plenum part is designed to collect the fission product gas produced by the nuclear fission reaction of the pellet, to alleviate the increase in internal pressure due to the increase in the products, and to extend the creep rupture life of the element due to the increase in pressure. and a spring that restricts the axial direction of each pellet so that its position does not move during transportation.

被覆管には二つの主要な目的があり、第1は核燃料ペレ
ットと冷却材との間の化学反応を防ぐことで、第2は高
放射能物質である核分裂生成物が冷却材中に放出されな
いようにすることである。
The cladding has two main purposes: the first is to prevent chemical reactions between the nuclear fuel pellets and the coolant, and the second is to prevent highly radioactive fission products from being released into the coolant. It is to do so.

被覆管が局部的に破損すると冷却材が長寿命の半減期を
有する核分裂生成物で汚染することになり、プラントの
運転および管理に多大の障害をもたらすことになる。
Localized failure of the cladding can result in contamination of the coolant with fission products that have long half-lives, resulting in significant disruption to plant operation and management.

また冷却材が通過する熱交換器やタービンの如き外部装
置も汚染されることにもなるため被覆管の破損を早期に
発見し、破損燃料に対する処理を講じる必要がある。
Furthermore, external devices such as heat exchangers and turbines through which the coolant passes are also contaminated, so it is necessary to detect damage to the cladding tube at an early stage and take measures to deal with the damaged fuel.

このため通常は原子炉冷却材および発生した気体の全体
的放射能は運転中監視されており、放射能が上昇すれば
装置内の何れかの被覆管に漏洩が起ったとみられるので
過度の冷却材の汚染が生じる以前に原子炉の運転を停止
している。
For this reason, the overall radioactivity of the reactor coolant and generated gas is usually monitored during operation, and if the radioactivity increases, it is likely that a leak has occurred in one of the cladding tubes in the equipment, so excessive Reactor operations were shut down before coolant contamination occurred.

どの燃料集合体の中の燃料要素が破損したのかを調べる
ためには、これまで各々の燃料集合体から流出する冷却
材から連続的または間欠的に試料を採取して原子炉から
離れた所に設けられた検査室で各試料の放射能を監視す
る試みがなされている。
In order to determine which fuel element in a fuel assembly has failed, it has been necessary to continuously or intermittently take samples of the coolant flowing from each fuel assembly and to collect them at a location remote from the reactor. Attempts are being made to monitor the radioactivity of each sample in established laboratories.

しかしながら、間欠的に試料を採取すると所定の燃料集
合体に対するサンプリングの合間に著しい故障が生じて
、冷却材が問題になるほど汚染される恐れがある。
However, intermittent sampling can result in significant failures between samples for a given fuel assembly, resulting in problematic contamination of the coolant.

また炉内に数百本も装荷されている燃料集合体の各々か
ら試料を連続的に採取して検査するには膨大な量の装置
、試料採取管の複雑な解析装置が必要になるなどの問題
点がある。
In addition, in order to continuously collect and inspect samples from each of the hundreds of fuel assemblies loaded in the reactor, a huge amount of equipment and complicated analysis equipment for the sample collection tubes are required. There is a problem.

そこで、これらの問題点を解決するため各々の燃料棒又
は集合体、あるいはいくつかのグループに区分し、核燃
料棒に同位体レベルで混合組成の異なるタグガスと称す
る混合ガスを、あらかじめ封入しておき、破損燃料から
流出するタグガスをカバーガス又は冷却材中からサンプ
リングして、その組成を分析し破損燃料を同定すること
が試みられている。
Therefore, in order to solve these problems, nuclear fuel rods are divided into individual fuel rods or assemblies, or into several groups, and mixed gases called tag gases, which have different mixture compositions at the isotope level, are sealed in advance in the nuclear fuel rods. Attempts have been made to sample the tag gas flowing out from the damaged fuel from the cover gas or coolant, analyze its composition, and identify the damaged fuel.

タグガスとしては、原子炉構造材、核燃料物質、冷却材
、減速材などに対して不活性で、たとえばアルゴン、キ
セノン、ネオンなどの希ガスが1種又は混合されて使用
されている。
The tag gas is inert to nuclear reactor structural materials, nuclear fuel materials, coolants, moderators, etc., and includes one or a mixture of rare gases such as argon, xenon, and neon.

従来タグガス入り核燃料棒はたとえば、アルミニウム、
ステンレス鋼などのカプセル内に組成の分かったタグガ
スを封入し、燃料棒の製造時に被覆管内に挿入し、被覆
管を密封した後、カプセルを開封して燃料棒内に充満さ
せることが考えられているが、量産される核燃料棒のよ
うな生産ラインで各々の核燃料棒毎に組成の異るタグガ
スを被覆管の密封溶接時に所定量づつを封入することは
困難であり、かつ製造工数を多くし、コスト高になり好
しいものとは云えない。
Conventional nuclear fuel rods containing tag gas are made of, for example, aluminum,
One idea is to seal a tag gas of known composition into a capsule made of stainless steel or other material, insert it into a cladding tube during fuel rod manufacture, seal the cladding tube, and then open the capsule to fill the fuel rod. However, on a production line for mass-produced nuclear fuel rods, it is difficult to fill each nuclear fuel rod with a predetermined amount of tag gas, which has a different composition, when the cladding tube is hermetically welded, and it also increases the number of manufacturing steps. , which is not desirable due to high cost.

そこで従来の上記のカプセルを被覆管密封後に開封する
方法としてはカプセルの開口部を低溶融金属のシール材
でシールし、これを核燃料棒の使用温度又は局部加熱で
前記シール材を溶融開封しタグガスを被覆管内に放出さ
せる核燃料棒も知られている。
Therefore, the conventional method of opening the above-mentioned capsule after sealing the cladding tube is to seal the opening of the capsule with a low-melting metal sealing material, melt the sealing material at the working temperature of the nuclear fuel rod or with local heating, and open the capsule with the tag gas. Nuclear fuel rods are also known in which nuclear fuel is released into a cladding tube.

その他の方法としては被覆管内に装填されたカプセルを
外部から衝撃力を加えて薄膜を破る方法も知られている
Another known method is to apply impact force from the outside to a capsule loaded in a cladding tube to break the thin film.

しかしこれらの方法は、溶融したシール材が燃料ペレッ
トおよび被覆管と接触し、反応物を生成し、時には被覆
管を腐食さ昼で破損の原因となる。
However, in these methods, the molten sealant comes into contact with the fuel pellets and cladding, producing reactants and sometimes corroding the cladding, causing damage.

又衝撃力を加えるためには可動物体を封入しておくか核
燃料棒自身にも衝撃を加えなげればならず核燃料棒のプ
レナム部の有効容積を減少させる結果燃料の使用寿命を
短くしなげればならない欠点がある。
In addition, in order to apply an impact force, it is necessary to encapsulate a movable object or apply an impact to the nuclear fuel rod itself, which reduces the effective volume of the plenum of the nuclear fuel rod and shortens the service life of the fuel. There are certain drawbacks.

本発明の目的は上記の欠点を除去するためになされたも
ので、ガスプレナム部の容積を低下させる割合を少なく
、かつ確実に開封して被覆管内にタグガスを放出し、し
かも被覆管および燃料ペレットに腐食等の問題の残らな
いタグガス入り核燃料棒を提供することにある。
An object of the present invention has been made to eliminate the above-mentioned drawbacks.The purpose of the present invention is to reduce the rate of decrease in the volume of the gas plenum, to reliably open the seal and release tag gas into the cladding tube, and to release the tag gas into the cladding tube and fuel pellets. An object of the present invention is to provide a nuclear fuel rod containing tag gas that does not cause problems such as corrosion.

すなわち、本発明は、核燃料物質を装填した長尺被覆管
内のプレナム部にダグガスを充填したカプセルを封入し
て、管端を密栓した核燃料棒において、前記カプセルの
1端面の一部を薄膜部で構成し、この薄膜部に対向して
突刺部を設け、更にこの突刺部を駆動する位置に少なく
とも1つの熱膨張係数の異る材料より構成された円板状
バイメタルを配置し前記バイメタルの熱変形により前記
突刺部で前記薄膜部を開封するよう構成したことを特徴
とする核燃料棒である。
That is, the present invention provides a nuclear fuel rod in which a capsule filled with Doug gas is enclosed in the plenum part of a long cladding tube loaded with nuclear fuel material, and the tube end is hermetically sealed, in which a part of one end surface of the capsule is made of a thin film part. A protrusion is provided opposite to the thin film part, and a disc-shaped bimetal made of at least one material having a different coefficient of thermal expansion is disposed at a position where the protrusion is driven, and the bimetal is thermally deformed. The nuclear fuel rod is characterized in that the thin film portion is opened by the piercing portion.

さらには前記円板状バイメタルを熱膨張差の発生によっ
て反転変位可能な皿形状とし、この反転に伴う変位と衝
撃力により隔膜を開封する前記核燃料棒である。
Further, in the nuclear fuel rod, the disk-shaped bimetal is formed into a dish shape that can be reversed due to the generation of a difference in thermal expansion, and the diaphragm is opened by the displacement and impact force accompanying this reversal.

以下に本発明の一実施例を第1図乃至第3図に基づいて
詳細に説明する。
An embodiment of the present invention will be described in detail below with reference to FIGS. 1 to 3.

第1図は本発明に係るタグガスカプセル1を核燃料棒2
のプレナム部2aに挿入したものを示し、符号2bは被
覆管を示し、符号2Cはペレットを示し、符号2dはス
プリングを示す。
FIG. 1 shows a tag gas capsule 1 according to the present invention and a nuclear fuel rod 2.
2b is a cladding tube, 2C is a pellet, and 2d is a spring.

タグカプセル1はチューブ1aの一端にガス導入管4を
有する端板4aが設けられ、他端には開封時開口部を形
成する薄膜部6が端板5aに1体的に構成されている。
In the tag capsule 1, an end plate 4a having a gas introduction pipe 4 is provided at one end of a tube 1a, and a thin film portion 6 forming an opening when the seal is opened is integrally formed with the end plate 5a at the other end.

ガス導入管4のタグガス導入口5はタグガス3を所定量
カプセル1に導入後は圧接又は溶接等で密封される。
The tag gas inlet 5 of the gas inlet pipe 4 is sealed by pressure welding, welding, etc. after a predetermined amount of the tag gas 3 is introduced into the capsule 1.

かくしてタグガス3はカプセル1内に所定量が封入され
る。
In this way, a predetermined amount of the tag gas 3 is sealed in the capsule 1.

一方、薄膜部6に対向して突刺部材11の有刺端7が薄
膜部6から常温で、一定の間隔(G)をおいて配置され
ている。
On the other hand, the barbed end 7 of the piercing member 11 is disposed facing the thin film part 6 at a constant distance (G) from the thin film part 6 at room temperature.

さらに突刺部材11の背部には熱膨張係数の異る材料よ
り製作された円板状バイメタル10が複数個積層配置さ
れ、各々の円板状バイメタル10は高膨張係数の材料面
(以下高膨張側と呼ぶ)を相互に背合せに配置されてお
り、これら部材はカプセルチューブ1aの薄膜部6側端
部に装着されたハウジング9内に収納されている。
Furthermore, a plurality of disc-shaped bimetals 10 made of materials with different thermal expansion coefficients are stacked on the back of the piercing member 11, and each disc-shaped bimetal 10 has a material side with a high expansion coefficient (hereinafter referred to as a high expansion side). These members are housed in a housing 9 attached to the end of the capsule tube 1a on the thin film portion 6 side.

又ハウジング9とバイメタル10にはタグガスの通気孔
8゜8aが設げられている。
Further, the housing 9 and the bimetal 10 are provided with tag gas vents 8.8a.

ところで第2図aに示すように円板状パイメタル10は
前述のように高膨張側10aと低膨張側10bを有する
ため、これが加熱されると第2図すのようにワン曲し円
板状バイメタル10はあたかも皿バネ状に変形する。
By the way, as shown in FIG. 2a, the disk-shaped piemetal 10 has a high expansion side 10a and a low expansion side 10b as described above, so when it is heated, it bends into a disk shape as shown in FIG. The bimetal 10 deforms as if it were a disc spring.

この結果常温で厚さくhl)のものが加熱状態ではその
温度に比例して見掛上の厚さくh2)に増大する。
As a result, a material having a thickness hl) at room temperature increases to an apparent thickness h2) in a heated state in proportion to the temperature.

かくして背合せに積層された各バイメタル10の変位に
よって、第1図の薄膜部6との間隔qは消失し最終的に
は有刺端7は、第3図に示すように薄膜部6を貫通して
カプセル1内のタグガス3を核燃料棒2内に放散させる
ことができる。
In this way, due to the displacement of each bimetal 10 stacked back to back, the distance q from the thin film part 6 shown in FIG. 1 disappears, and finally the barbed end 7 penetrates the thin film part 6 as shown in FIG. The tag gas 3 in the capsule 1 can be diffused into the nuclear fuel rod 2 by doing so.

ここで薄膜部6の長さと、バイメタル10のワン曲係数
と厚さおよび枚数はそのタグガスカプセル1の開封温度
条件に合せて任意に設計することが可能である。
Here, the length of the thin film portion 6 and the one-curve coefficient, thickness, and number of bimetallic parts 10 can be arbitrarily designed in accordance with the opening temperature conditions of the tag gas capsule 1.

また有刺端Iと薄膜部6との間隔Gの設定もこれらの条
件の他、カプセルおよび燃料棒の製造工程や取扱いを考
慮して選択できる。
In addition to these conditions, the setting of the distance G between the barbed end I and the thin film portion 6 can also be selected taking into consideration the manufacturing process and handling of the capsule and fuel rod.

次に本発明の他の実施例について第4図、第5図で説明
する。
Next, another embodiment of the present invention will be described with reference to FIGS. 4 and 5.

第4図に示すように中央に通気孔8aを有する円板状バ
イメタル20をダイス15を用いて先端が半球状の凸面
及び凹面を有するパンチ16゜17で僅かに皿形状に成
形加工する。
As shown in FIG. 4, a disc-shaped bimetal 20 having a ventilation hole 8a in the center is formed into a slightly dish-shaped shape using a die 15 and a punch 16.degree. 17 having a hemispherical convex and concave tip.

この時高膨張側20aを円弧の外面側に向く凹状にする
At this time, the high expansion side 20a is made into a concave shape facing toward the outer surface of the arc.

次にこの皿形状の円板状バイメタル20を第5図aに示
すように成形時の逆の凹状、つまり高膨張側が図示の如
(円弧の内側になるように反転変位させ、その中央に有
刺端7を有する部材11aをとりつげる。
Next, as shown in FIG. 5a, this dish-shaped disc-shaped bimetal 20 is inverted and displaced so that the concave shape is opposite to that when molded, that is, the high expansion side is inside the arc (as shown in the figure), and a The member 11a having the barbed end 7 is attached.

これを薄膜部6の近傍に、ハウジング9aに加工した突
起部21に円板状バイメタル200周縁部が支持される
ように配置する。
This is placed near the thin film portion 6 so that the peripheral edge of the disc-shaped bimetal 200 is supported by the protrusion 21 machined into the housing 9a.

かくして反転変位された皿形状の円板状バイメタル20
は加熱に伴って次第に変形し、ついには成形時の皿状に
変位する瞬間において衝撃的に第5図すに示す有刺端7
が薄膜部6を貫通し、タグガス3を核燃料棒2内のプレ
ナム部2aに放散することができる。
The dish-shaped disc-shaped bimetal 20 is thus reversely displaced.
The barbed end 7 gradually deforms as it is heated, and finally, at the moment when it is displaced into a dish shape during molding, the barbed end 7 shown in FIG.
penetrates the thin film portion 6 and can diffuse the tag gas 3 into the plenum portion 2a within the nuclear fuel rod 2.

ここで用いるバイメタルはFe。Ni、Cr を全成分
とする2種類の合金の張合材でよい。
The bimetal used here is Fe. A composite material of two types of alloys containing Ni and Cr as all components may be used.

以上の通り本発明によれば燃料棒の原子炉内での破損を
検出するためのタグガスを封入したカプセルを炉内の任
意の温度下で開封することができる。
As described above, according to the present invention, a capsule filled with tag gas for detecting damage to a fuel rod in a nuclear reactor can be opened at any temperature in the reactor.

さらにプレナム部の有効容積を減少させる割合を少なく
し、かつ燃料ペレットおよび被覆管に対して腐食性の心
配もなく確実に炉内でタグガスカプセルを開封できるな
どの効果がある。
Furthermore, the effective volume of the plenum part is reduced at a reduced rate, and the tag gas capsule can be reliably opened in the furnace without fear of corrosion to the fuel pellets and cladding.

このような構造を有するタグガスカプセル入りの核燃料
棒の製造はその規格化された製造ラインにカプセル開封
のための特殊な工程も必要とせず従って核燃料棒の検査
不良品からカプセルの回収し再使用も可能であり、燃料
棒の組立自効化に対しても有効なタグガスカプセル入り
の各燃料棒を提供できる。
The production of nuclear fuel rods with tag gas capsules having this structure does not require any special process for opening the capsules on the standardized production line, and therefore it is possible to recover and reuse capsules from defective nuclear fuel rods during inspection. It is also possible to provide each fuel rod containing a tag gas capsule, which is also effective for making the assembly of fuel rods more efficient.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明の一実施例を示す部分縦断面図、第2図
a、bは第1図にて使用する開封部バイメタルの熱変位
を説明する図、第3図は第1図の開封構造部の開封状態
を説明するため拡大して示す断面図、第4図は本発明の
他の実施例に使用する皿形状の円板状バイメタルの成形
加工を説明する図、第5図a、bは本発明の他の実施例
を要部を拡大して示す断面図である。 1・・・・・・カプセル、2・・・・・・核燃料棒、2
a・・・・・・プレナム部、2c・・・・・・ペレット
、3・・・・・・タグガス、4・・・・・・ガス導入管
、6・・・・・・薄膜部、7・・・・・・有刺端、8.
8a・・・・・・通気孔、9・・・・・・ハウジング、
10゜20・・・・・・円板状バイメタル。
FIG. 1 is a partial vertical sectional view showing an embodiment of the present invention, FIGS. 2a and b are diagrams explaining thermal displacement of the opening bimetal used in FIG. 1, and FIG. FIG. 4 is an enlarged cross-sectional view to explain the unsealed state of the unsealing structure; FIG. 4 is a diagram illustrating the forming process of a dish-shaped disc-shaped bimetal used in another embodiment of the present invention; FIG. 5a , b are sectional views showing enlarged main parts of other embodiments of the present invention. 1... Capsule, 2... Nuclear fuel rod, 2
a...Plenum part, 2c...Pellet, 3...Tag gas, 4...Gas introduction pipe, 6...Thin film part, 7 ...barbed end, 8.
8a...Vent hole, 9...Housing,
10゜20・・・Disc-shaped bimetal.

Claims (1)

【特許請求の範囲】 1 核燃料物質を装てんした長尺被覆管内のプレナム部
に、タグガスを充填したカプセルを封入して、管端を密
栓したる核燃料棒において、前記カプセルの1端面の一
部を薄膜部で構成し、この薄膜部に対向して突刺部を設
け、更にこの突刺部を駆動する位置に少なくとも1つの
熱膨張係数の異なる材料より構成された円板状バイメタ
ルを配置し前記バイメタルの熱変形により前記突刺部で
前記薄膜部を開封するよう構成したことを特徴とするタ
グカプセル入り核燃料棒。 2 円板状バイメタルを熱膨張差によって反転変位する
皿形状としたことを特徴とする特許請求範囲第1項記載
の核燃料棒。
[Scope of Claims] 1. In a nuclear fuel rod in which a capsule filled with tag gas is sealed in the plenum part of a long cladding tube loaded with nuclear fuel material and the tube end is tightly plugged, a part of one end surface of the capsule is sealed. A thin film part is provided, a protrusion is provided opposite to the thin film part, and a disc-shaped bimetal made of at least one material having a different coefficient of thermal expansion is disposed at a position where the protrusion is driven. A nuclear fuel rod containing a tag capsule, characterized in that the thin film part is opened by the piercing part by thermal deformation. 2. The nuclear fuel rod according to claim 1, wherein the disc-shaped bimetal has a dish shape that is reversely displaced due to a difference in thermal expansion.
JP54079060A 1979-06-25 1979-06-25 nuclear fuel rod Expired JPS5833517B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP54079060A JPS5833517B2 (en) 1979-06-25 1979-06-25 nuclear fuel rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP54079060A JPS5833517B2 (en) 1979-06-25 1979-06-25 nuclear fuel rod

Publications (2)

Publication Number Publication Date
JPS564094A JPS564094A (en) 1981-01-16
JPS5833517B2 true JPS5833517B2 (en) 1983-07-20

Family

ID=13679340

Family Applications (1)

Application Number Title Priority Date Filing Date
JP54079060A Expired JPS5833517B2 (en) 1979-06-25 1979-06-25 nuclear fuel rod

Country Status (1)

Country Link
JP (1) JPS5833517B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6255326A (en) * 1985-09-04 1987-03-11 Ritsukou Kensetsu Kk Underwater leveler
JPS62164920A (en) * 1986-01-16 1987-07-21 Ritsukou Kensetsu Kk Leveler for rubble under water

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57125385A (en) * 1981-01-28 1982-08-04 Tokyo Shibaura Electric Co Tag gas sealing body

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6255326A (en) * 1985-09-04 1987-03-11 Ritsukou Kensetsu Kk Underwater leveler
JPS62164920A (en) * 1986-01-16 1987-07-21 Ritsukou Kensetsu Kk Leveler for rubble under water

Also Published As

Publication number Publication date
JPS564094A (en) 1981-01-16

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