JPS626194A - Fuel aggregate for nuclear reactor - Google Patents

Fuel aggregate for nuclear reactor

Info

Publication number
JPS626194A
JPS626194A JP60145236A JP14523685A JPS626194A JP S626194 A JPS626194 A JP S626194A JP 60145236 A JP60145236 A JP 60145236A JP 14523685 A JP14523685 A JP 14523685A JP S626194 A JPS626194 A JP S626194A
Authority
JP
Japan
Prior art keywords
fuel
fuel assembly
output
burnable poison
reactor
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.)
Granted
Application number
JP60145236A
Other languages
Japanese (ja)
Other versions
JPH0317317B2 (en
Inventor
仁紫 明人
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.)
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
Power Reactor and Nuclear Fuel Development Corp
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 Power Reactor and Nuclear Fuel Development Corp filed Critical Power Reactor and Nuclear Fuel Development Corp
Priority to JP60145236A priority Critical patent/JPS626194A/en
Priority to CA000512720A priority patent/CA1268563A/en
Publication of JPS626194A publication Critical patent/JPS626194A/en
Publication of JPH0317317B2 publication Critical patent/JPH0317317B2/ja
Granted 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

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、原子炉出力運転中に新たに装荷した燃料集合
体の燃焼初期における出力上昇速度を制御するために、
燃料集合体内の大部分の燃料ペレッ1に可燃性毒物を低
濃度で分散させ、出力運転中に燃料装荷を行なえるよう
にした原子炉燃料集合体に関する。
[Detailed Description of the Invention] [Industrial Application Field] The present invention provides a method for controlling the power increase rate at the initial stage of combustion of a newly loaded fuel assembly during reactor power operation.
This invention relates to a nuclear reactor fuel assembly in which a burnable poison is dispersed at a low concentration in most of the fuel pellets 1 in the fuel assembly, so that fuel can be loaded during power operation.

[従来の技術] 一般に圧力管型動力炉は、原子炉を停止することなしに
出力運転中でも燃料交換を行うことができるという大き
な特徴を有する。しかし実際には、出力運転中に燃料交
換を行うと装荷した新燃料集合体およびその周囲の燃料
集合体は装荷と共に急激に(僅か2時間程度で)出力が
上昇する。この出力上昇は新燃料集合体と取り出した使
用済燃料集合体との無限増倍率の差が大きいほど大きい
[Prior Art] In general, a pressure tube power reactor has a major feature in that fuel can be replaced even during output operation without shutting down the reactor. However, in reality, when fuel is exchanged during power operation, the output of the newly loaded new fuel assembly and the surrounding fuel assemblies increases rapidly (in only about 2 hours) as the new fuel assembly is loaded. This increase in output increases as the difference in infinite multiplication factor between the new fuel assembly and the removed spent fuel assembly increases.

燃料集合体の出力が急激に上昇すると、燃料ペレットと
被覆管との熱膨張差により燃料ペレットが被覆管に接触
し、更に被覆管を押し拡げ損傷を与える可能性がある。
When the output of the fuel assembly suddenly increases, the fuel pellets may come into contact with the cladding tube due to the difference in thermal expansion between the fuel pellets and the cladding tube, and may further push the cladding tube open and cause damage.

そこで従来技術では燃料交換を原子炉の停止中に行うバ
ンチ方式が採用され、原子炉を起動する時には原子炉の
出力上昇速度を調整して燃料集合体の出力上昇速度を小
さくする方法が採られている。
Therefore, in the conventional technology, a bunch method is adopted in which fuel is exchanged while the reactor is stopped, and when the reactor is started up, a method is adopted in which the rate of increase in the output of the reactor is adjusted to reduce the rate of increase in the output of the fuel assembly. ing.

[発明が解決しようとする問題点] 原子炉の停止中にバッチ方式で燃料交換を行い、起動時
に原子炉の出力上昇速度を調整して燃料集合体の出力上
昇速度を小さくすれば、燃料ベレットは圧縮応力により
その高温中心部がクリープ変形し、また被覆管は引張り
応力によりクリープ変形するから、該被覆管に生じる応
力が緩和され燃料集合体の健全性が確保される。
[Problems to be solved by the invention] If the fuel is exchanged in a batch manner while the reactor is stopped, and the rate of increase in the output of the reactor is adjusted at startup to reduce the rate of increase in the output of the fuel assembly, the fuel pellets can be reduced. Since the high-temperature center of the fuel cell creep deforms due to compressive stress, and the cladding tube creep deforms due to tensile stress, the stress generated in the cladding tube is alleviated and the integrity of the fuel assembly is ensured.

しかしながらこのような燃料交換方法では原子炉の出力
運転中に燃料交換を行なえるという圧力管型原子炉の大
きな特徴の一つが損なわれ、運転稼動率が低下するばか
りでなく燃料利用率も低下するという大きな欠点が生じ
る。
However, this type of fuel exchange method loses one of the major features of pressure tube reactors, which is that fuel can be exchanged while the reactor is operating at its output, resulting in not only a decrease in operating availability but also a decrease in fuel utilization. This results in a major drawback.

本発明の目的は、上記のような従来技術の欠点を解消し
、原子炉の出力運転中に燃料装荷を行っても新燃料集合
体および装荷チャンネル回りの燃料集合体の出力上昇を
抑制できるとともに、新燃料集合体の燃焼初期の出力上
昇速度の制御が可能であり、燃料の健全性が確保され、
燃料利用率や運転稼動率を著しく向上させることができ
るような改良された原子炉燃料集合体を提供することに
ある。
An object of the present invention is to eliminate the drawbacks of the prior art as described above, and to suppress the increase in output of new fuel assemblies and fuel assemblies around the loading channel even if fuel is loaded during power operation of a nuclear reactor. , it is possible to control the rate of increase in output in the initial stage of combustion of the new fuel assembly, ensuring the integrity of the fuel,
An object of the present invention is to provide an improved nuclear reactor fuel assembly that can significantly improve fuel utilization and operational availability.

[問題点を解決するための手段] 上記のような目的を達成できる本発明は、燃料集合体内
の大部分の燃料ベレットに可燃性毒物を、その燃焼率が
燃焼の初期で時間的に変化するような低濃度で分散させ
た原子炉燃料集合体であり、該可燃性毒物により燃料集
合体の出力上昇速度を制御し、出力運転中に燃料装荷を
行なえるようにした点に大きな特徴を存するものである
[Means for Solving the Problems] The present invention, which can achieve the above-mentioned objects, contains a burnable poison in most of the fuel pellets in a fuel assembly, the combustion rate of which changes over time at the initial stage of combustion. It is a reactor fuel assembly that is dispersed at a low concentration such as burnable poison, and its major feature is that the output increase rate of the fuel assembly is controlled by the burnable poison, and fuel can be loaded during output operation. It is something.

ここで「燃料集合体の大部分の燃料ベレット」とは、燃
料集合体中に存在する燃料ベレットのうちのほぼ半数程
度以上のことをいい、より好ましくは8割程度以上であ
る。燃料集合体は多数の燃料ベレットを装填した燃料棒
を多数本配列した構成であ・す、出力分布は各燃料ベレ
ットで一様ではなく、一般に外側に配列された燃料棒の
方が高いし、また各燃料棒についてみれば両端部より中
央部はど高い。従って可燃性毒物を入れる燃料ベレット
の割合が半数程度と少ない場合には、特に出力上昇を制
御したい領域の燃料ペレットを選んで該可燃性毒物を入
れればよい。
Here, "most of the fuel pellets in the fuel assembly" refers to approximately half or more of the fuel pellets present in the fuel assembly, and more preferably approximately 80% or more. A fuel assembly is composed of a large number of fuel rods loaded with a large number of fuel pellets arranged in a row.The power distribution is not uniform for each fuel pellet, and the fuel rods arranged on the outside are generally higher in power. Also, looking at each fuel rod, the center is higher than both ends. Therefore, if the proportion of fuel pellets containing burnable poison is as small as about half, it is sufficient to select fuel pellets in a region where it is particularly desired to control the increase in output and insert the burnable poison.

燃料集合体内に分散する可燃性毒物としては例えばガド
リニア(Gd、o3)を用いることができ、原子炉燃料
である二酸化ウラン粉末に均一に混入した後、焼結した
酸化物燃料ペレットを用いる構成であってよい。この場
合ガドリニアの濃度は0.2%程度以下、好ましくは0
.05%程度の低濃度とする。
For example, gadolinia (Gd, O3) can be used as the burnable poison dispersed within the fuel assembly, and after being uniformly mixed into uranium dioxide powder, which is the reactor fuel, sintered oxide fuel pellets are used. It's good. In this case, the concentration of gadolinia is about 0.2% or less, preferably 0.
.. The concentration should be as low as 0.05%.

可燃性毒物としては、上記ガドリニウムの他、ホウ素、
カドミウム、ジスプロシウム等を用いることができる。
In addition to the above gadolinium, burnable poisons include boron,
Cadmium, dysprosium, etc. can be used.

ところで可燃性毒物を混入した燃料ベレットを用いる燃
料集合体は従来公知であるが、これは炉心の出力分布を
平坦化するためのものである。可燃性毒物により余剰反
応度や出力を抑制して適切な余剰反応度および適切な出
力に設定し、これが定常的に維持されるように高い1度
の可燃性毒物を燃料集合体内で局所的(通常、1割程度
の燃料ベレット)に混入または配置して長期間その効果
を持続させているのであり、本願発明が意図している燃
料集合体の出力上昇速度の制御とは全く異なる技術であ
る。
Incidentally, fuel assemblies using fuel pellets mixed with burnable poisons are conventionally known, and are intended to flatten the power distribution of the reactor core. Excess reactivity and output are suppressed by burnable poisons and set to appropriate surplus reactivity and output, and in order to maintain this constant level, high degree burnable poisons are applied locally within the fuel assembly ( This is a technology that is completely different from the control of the rate of increase in output power of a fuel assembly as intended by the present invention. .

[作用] 燃料集合体の大部分の燃料ベレットに低濃度で分散され
ている可燃性毒物は、その燃料率が燃焼の初期で時間的
に変化し、該可燃性毒物の燃焼による反応度の変化、出
力変化を利用して15日間程度で装荷した燃料集合体の
出力がほぼ所定出力状態に達するように出力上昇速度の
制御を行うことができる。
[Effect] The burnable poison dispersed at a low concentration in the fuel pellets of most of the fuel assemblies has a fuel rate that changes over time at the initial stage of combustion, and a change in reactivity due to the combustion of the burnable poison. By using the output change, it is possible to control the output increase rate so that the output of the loaded fuel assembly reaches approximately a predetermined output state in about 15 days.

[実施例] 以下、本発明の一実施例について更に詳しく説明する。[Example] Hereinafter, one embodiment of the present invention will be described in more detail.

燃料集合体としての基本的な構成は従来のものと同様で
ある。第1図は可燃性毒物を含有する燃料ベレット10
を示す、この燃料ベレット10は、可燃性毒物としてガ
ドリニア(Ca、O,)を原子燃料である二酸化ウラン
粉末と均一に混合した後、円柱状に成形し焼結したもの
である。ただし本発明では、ガドリニアはその燃焼率が
燃焼の初期に急激に変化するような低い濃度で混入され
ている。
The basic structure of the fuel assembly is the same as the conventional one. Figure 1 shows a fuel pellet 10 containing burnable poison.
This fuel pellet 10 is made by uniformly mixing gadolinia (Ca, O,) as a burnable poison with uranium dioxide powder as a nuclear fuel, and then forming the mixture into a cylindrical shape and sintering it. However, in the present invention, gadolinia is mixed in at such a low concentration that its combustion rate changes rapidly at the beginning of combustion.

このような燃料ベレット10は、第2図に示すようにジ
ルカロイ等からなる被覆管12内に多数充填され、その
両端がそれぞれ端栓14によって密封されて燃料棒16
が構成される。燃料集合体20は、第3図および第4図
に示すように、28本の燃料棒16を束にしたクラスタ
型である。燃料棒16は円形圧力管内に装荷されるため
三層の同心円周上に配列され、上部タイブレート22お
よび下部タイブレート24で固定されると共に、水平方
向の構造的安定を図るためスペーサ26が取り付けられ
る。なお符号2日はスペーサ支持棒を示す。
As shown in FIG. 2, a large number of such fuel pellets 10 are filled in a cladding tube 12 made of Zircaloy or the like, and both ends of the cladding tube 12 are sealed with end plugs 14 to form a fuel rod 16.
is configured. The fuel assembly 20, as shown in FIGS. 3 and 4, is a cluster type in which 28 fuel rods 16 are bundled. Since the fuel rods 16 are loaded into the circular pressure tube, they are arranged in three layers of concentric circles, fixed by an upper tie plate 22 and a lower tie plate 24, and spacers 26 are attached to ensure horizontal structural stability. Note that the number 2 indicates a spacer support rod.

前記のように燃料ペレットIOの違いを除けば、他の構
成は従来技術と同様であるから、それをそのまま利用す
ることができる0本発明が従来技術と顕著に相違する点
は、第1に燃料ベレットの組成の相違であり、第2に可
燃性毒物の燃料集合体内での分散状態の相違である。つ
まり本発明では可燃性毒物の混入または配置の濃度が低
く、また可燃性毒物が燃料集合体中の大部分の燃料ベレ
ットに存在する。
As mentioned above, except for the difference in fuel pellet IO, the other configurations are the same as the conventional technology, so it can be used as is.The present invention is significantly different from the conventional technology. The difference is in the composition of the fuel pellets, and the second difference is in the state of dispersion of the burnable poison within the fuel assembly. In other words, in the present invention, the concentration of the burnable poison is low, and the burnable poison is present in most of the fuel pellets in the fuel assembly.

第5図は0.05%のガドリニアを均一分散させた原子
炉燃料集合体の燃焼度に対する無限増倍率の関係を示す
グラフである。同図において実線は本発明を適用した場
合であり、破線は可燃性毒物を用いない場合である。可
燃性毒物を均一に分散した原子炉燃料集合体を出力運転
中の動力炉に装荷しても、この可燃性毒物による中性子
吸収の効果のために装荷した新しい原子炉燃料集合体は
高出力とはならない。新燃料集合体の無限増倍率は交換
された使用済み燃料集合体のそれより小さいから、交換
チャンネル及びその回りのチャンネルでの出力は交換前
の出力よりも小さい、装荷直後の無限増倍率は約0.5
である。
FIG. 5 is a graph showing the relationship between the infinite multiplication factor and the burnup of a nuclear reactor fuel assembly in which 0.05% gadolinia is uniformly dispersed. In the figure, the solid line shows the case where the present invention is applied, and the broken line shows the case where no burnable poison is used. Even if a nuclear reactor fuel assembly with burnable poison evenly dispersed is loaded into a power reactor that is operating at high output, the new nuclear reactor fuel assembly loaded will not be able to achieve high output due to the neutron absorption effect of this burnable poison. Must not be. Since the infinite multiplication factor of the new fuel assembly is smaller than that of the replaced spent fuel assembly, the output in the replacement channel and the channels around it is smaller than the output before replacement, and the infinite multiplication factor immediately after loading is approximately 0.5
It is.

可燃性毒物の燃焼と共にこの燃料集合体の無限増倍率が
回復し、通常、1日当たり約20MWd/を燃焼するか
ら、約5日後に交換された使用済み燃料集合体とほぼ同
じ無限増倍率になり、交換チャンネルおよびその回りの
チャンネルはほぼ交換前の出力状態に回復する。装荷後
約15日間程度が経過すると可燃性毒物が消滅し無限増
倍率は約1.2程度となり、所定の出力状態に達する。
As the burnable poison burns, the infinite multiplication factor of this fuel assembly is restored, and since it normally burns about 20 MWd/day, the infinite multiplication factor becomes almost the same as that of the spent fuel assembly that was replaced after about 5 days. , the replaced channel and the channels around it are restored to almost their pre-replacement output state. When about 15 days have passed after loading, the burnable poison disappears, the infinite multiplication factor becomes about 1.2, and a predetermined output state is reached.

従って、この血化期間は300MWd/を程度である。Therefore, this blood formation period is approximately 300 MWd/.

この原子炉燃料集合体の出力上昇速度は、約0.1%パ
ワー/時となり、また交換チャンネルの回りの燃料集合
体の出力上昇速度はそれ以下であるから、原子炉起動時
に実施している出力上昇速度制限より充分低くすること
ができる。
The power increase rate of this reactor fuel assembly is approximately 0.1% power/hour, and the power increase rate of the fuel assemblies around the exchange channel is less than that, so this is carried out at reactor startup. It can be made sufficiently lower than the output increase speed limit.

なお上記の実施例では、一種類の可燃性毒物を含有させ
たベレットを原子炉燃料集合体内においてほぼ一様に配
置しているが、原子炉燃料集合体内の燃料棒位置に応じ
て可燃性毒物の濃度を変えれば、燃料棒毎の出力上昇速
度の調整も行うことが可能である。
In the above example, the pellets containing one type of burnable poison are arranged almost uniformly in the reactor fuel assembly, but the burnable poison By changing the concentration of fuel, it is also possible to adjust the rate of increase in output power for each fuel rod.

出力分布平坦化のために濃度の高い可燃性毒物を含有さ
せる技術と本発明とを組み合わせることもでき、その場
合にも上記実施例の場合と同様に燃料集合体の出力上昇
速度を調整することができる。その−例を第6図に示す
。同図において実線は本発明方法を適用した場合(Gd
−0,08%の25本の燃料棒とGd−1,0%の4本
の燃料棒を用いた場合)であり、破線は従来の可燃性毒
物なしの場合と従来の出力平坦化法(高濃度可燃性毒物
の局所的混入)による場合(Gd−1,0%の3本の燃
料棒を用いた場合)である。同図から装荷した燃料集合
体の燃焼初期における出力上昇の制御と、その後に出力
平坦化が行われていることが明瞭に判るであろう。
It is also possible to combine the present invention with a technique for containing a highly concentrated burnable poison in order to flatten the power distribution, and in that case, the rate of increase in power of the fuel assembly can be adjusted in the same way as in the above embodiment. I can do it. An example thereof is shown in FIG. In the figure, the solid line indicates the case when the method of the present invention is applied (Gd
25 fuel rods with -0.08% Gd and 4 fuel rods with -1.0% Gd), and the dashed line shows the case without the conventional burnable poison and the case with the conventional power flattening method ( This is the case (when three fuel rods of Gd-1.0% are used) due to local contamination of high-concentration burnable poison. From the figure, it can be clearly seen that the power increase is controlled in the early stage of combustion of the loaded fuel assembly, and then the power is flattened.

[発明の効果] 本発明は上記のように燃料集合体内の大部分の燃料ペレ
ットに可燃性毒物を低濃度で分散させたから、原子炉出
力運転中に装荷した新燃料集合体およびその周囲の燃料
集合体の出力上昇を抑制でき、また新燃料の燃焼初期に
おける出力上昇速度を制御できるため、燃料の健全性を
確保することができ、出力運転中の燃料交換が可能とな
るため燃料利用率や運転稼動率を大幅に向上させること
ができるという優れた効果を奏する。
[Effects of the Invention] As described above, the present invention disperses burnable poisons at a low concentration in most of the fuel pellets in a fuel assembly, so that new fuel assemblies loaded during reactor power operation and the fuel around them It is possible to suppress the increase in the output of the assembly and control the rate of increase in output at the initial stage of combustion of new fuel, ensuring the integrity of the fuel, and making it possible to change the fuel during output operation, which improves the fuel utilization rate and This has the excellent effect of significantly improving the operating availability.

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

第1図は可燃性毒物を含有する燃料ペレットの斜視図、
第2図はそれを用いた燃料棒の一部破断説明図、第3図
はその燃料棒を組み込んだ原子炉燃料集合体の斜視図、
第4図はその断面図、第5図は本発明の一実施例による
燃料燃焼度と無限増倍率の関係を示すグラフ、第6図は
本発明の他の実施例による燃料燃焼度と無限増倍率の関
係を示すグラフである。 lO・・・可燃性毒物を含む燃料ペレット、12・・・
被覆管、16・・・燃料棒、20・・・燃料集合体、2
2・・・上部タイプレート、24・・・下部タイプレー
ト、26・・・スペーサ。 特許出願人  動力炉・核燃料開発事業団代  理  
人     茂  見     4第2図  第3図
Figure 1 is a perspective view of fuel pellets containing burnable poison;
Fig. 2 is a partially broken explanatory diagram of a fuel rod using the same, Fig. 3 is a perspective view of a nuclear reactor fuel assembly incorporating the fuel rod,
FIG. 4 is a cross-sectional view thereof, FIG. 5 is a graph showing the relationship between fuel burn-up and infinite multiplication factor according to one embodiment of the present invention, and FIG. 6 is a graph showing the relationship between fuel burn-up and infinite multiplication factor according to another embodiment of the present invention. It is a graph showing the relationship between magnifications. lO...Fuel pellets containing burnable poison, 12...
Cladding tube, 16... Fuel rod, 20... Fuel assembly, 2
2... Upper tie plate, 24... Lower tie plate, 26... Spacer. Patent applicant Representative of Power Reactor and Nuclear Fuel Development Corporation
Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 1、燃料集合体内の大部分の燃料ペレットに可燃性毒物
を、その燃焼率が燃焼の初期で時間的に変化するような
低い濃度で分散させ、出力運転中に燃料装荷を行えるよ
うにしたことを特徴とする原子炉燃料集合体。
1. The burnable poison is dispersed in most of the fuel pellets in the fuel assembly at such a low concentration that the combustion rate changes over time in the early stages of combustion, making it possible to load fuel during power operation. A nuclear reactor fuel assembly characterized by:
JP60145236A 1985-07-02 1985-07-02 Fuel aggregate for nuclear reactor Granted JPS626194A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP60145236A JPS626194A (en) 1985-07-02 1985-07-02 Fuel aggregate for nuclear reactor
CA000512720A CA1268563A (en) 1985-07-02 1986-06-27 Fuel assembly for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60145236A JPS626194A (en) 1985-07-02 1985-07-02 Fuel aggregate for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS626194A true JPS626194A (en) 1987-01-13
JPH0317317B2 JPH0317317B2 (en) 1991-03-07

Family

ID=15380480

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60145236A Granted JPS626194A (en) 1985-07-02 1985-07-02 Fuel aggregate for nuclear reactor

Country Status (2)

Country Link
JP (1) JPS626194A (en)
CA (1) CA1268563A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7426879B2 (en) 2002-05-08 2008-09-23 Sekisui Chemical Co., Ltd. Inspection method and inspection apparatus of reinforced concrete pipe

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS51101689A (en) * 1975-03-05 1976-09-08 Doryokuro Kakunenryo

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS51101689A (en) * 1975-03-05 1976-09-08 Doryokuro Kakunenryo

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7426879B2 (en) 2002-05-08 2008-09-23 Sekisui Chemical Co., Ltd. Inspection method and inspection apparatus of reinforced concrete pipe
US7530270B2 (en) 2002-05-08 2009-05-12 Sekisui Chemical Co., Ltd. Inspection method and inspection apparatus of reinforced concrete pipe

Also Published As

Publication number Publication date
JPH0317317B2 (en) 1991-03-07
CA1268563A (en) 1990-05-01

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