JPS5926091A - Wire spacer type nuclear fuel rod - Google Patents
Wire spacer type nuclear fuel rodInfo
- Publication number
- JPS5926091A JPS5926091A JP57134990A JP13499082A JPS5926091A JP S5926091 A JPS5926091 A JP S5926091A JP 57134990 A JP57134990 A JP 57134990A JP 13499082 A JP13499082 A JP 13499082A JP S5926091 A JPS5926091 A JP S5926091A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel rod
- fuel
- spacer
- wire
- 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
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
- Prostheses (AREA)
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】
本発明は、燃′)1′3Fビンの外周にJノイA7スベ
ーサを巻回し、そのワイヤによ・)て燃オ″11ビン間
I!8を保持づる構ン声の核燃料棒に関し、更に詳しく
は。DETAILED DESCRIPTION OF THE INVENTION The present invention has a structure in which a Jneu A7 spacer is wound around the outer periphery of the fuel bottle 1'3F, and the I!8 is held between the fuel oil 11 bins by the wire. For more information about the voice nuclear fuel rod.
流体振動に起因覆る燃料被覆質の摩耗を極力抑えつるよ
うな核燃料棒に閏づ−るものである。This is a device that is attached to a nuclear fuel rod that is capable of suppressing as much as possible the wear of the covering fuel cladding caused by fluid vibrations.
従来のワイA7スペーサ型核燃1′81棒で(ま、ガイ
置′;1被沼笛及びワイA7スペーサとも同じ成分〈通
畠5US31G)、同し冷間加工度の(A料か用いられ
ている。そのようなワイへ7スベー(す型)喪湿才々1
棒においては、核燃料棒が運転中に冷ム11月の(Aコ
体振動によって隣接核燃料棒と接触・衝突し、燃料被覆
管と隣接核燃料棒のスペーリワイ1アが(幾械的相互作
用を起こし被覆質が摩耗する。このような摩耗の発生は
、被覆色肉厚の局部的j[哉少を意味し、燃料ピンの健
全性計画条件が厳しくイTる。The conventional Y A7 spacer type nuclear fuel 1'81 rod (well, the same material as the 1 cover and the Y A7 spacer (Torihata 5US31G), the same degree of cold working (A material) was used. There is such a thing.
During operation, a nuclear fuel rod contacts and collides with an adjacent nuclear fuel rod due to cold body vibrations, and the fuel cladding tube and the spacer wire of the adjacent nuclear fuel rod (causing mechanical interaction). The coating material is worn out.The occurrence of such wear means a local decrease in the thickness of the coating color, and the conditions for planning the integrity of the fuel pin are strict.
摩耗を防止するため、核燃2′」棒間隔を狭めて振動を
小ざくする方法がある。しかし、このような方法は、当
然のことながら、燃料ピン同士の間隙が狭くなるため、
ピン束をラッパ管内に収納する作業が難しくなる。また
、燃オ′1ピン被覆管の外径、ワイヤの外径、及びラッ
パ管の内対面間距烏1(の製作公差を小さくし、燃料ピ
ン束の空隙密度(ビン1本当りの動き19る余裕)の値
が大きくならないようにづるととも(こ、組立てがτき
るよう上記空隙密度の値か負(こならないようにする必
要がある。この結果、被覆管、ワイ\ア、ラッパ管の製
作〜1ス1へか311入り−る欠点もある。史に、燃オ
′4ピン間隔が小さいため、スウIリングによるビン末
とラッパ1″(どの411互作用が生じやすくなり、燃
1’414命が短くなると91つだ欠点も生じる。In order to prevent wear, there is a method of reducing the vibration by narrowing the spacing between the nuclear fuel rods. However, this method naturally narrows the gap between the fuel pins, so
This makes it difficult to store the pin bundle inside the trumpet tube. In addition, we reduced the manufacturing tolerances of the outer diameter of the fuel pin cladding tube, the outer diameter of the wire, and the distance between the inner surfaces of the wrapper tube, and reduced the gap density of the fuel pin bundle (movement per bottle19). It is necessary to make sure that the value of the above-mentioned void density does not become too large, and also that the value of the above-mentioned void density does not become negative (so that the value of the cladding, wire, and trumpet tube There is also the drawback of entering the 311 into the 1st gear. Historically, because the spacing between the 4 pins is small, interaction between the end of the bottle and the 411 (which 411) is likely to occur due to the swivel ring, and the 411 '414 When life gets shorter, there are 91 drawbacks.
本発明の目的は、−1記のJ、う本−(1η来技((・
iの欠点を解消し、燃料ピン間隔を狭めることなく、製
造・組立が容易な仕様で、被覆管摩耗の生しない、安全
性の高いワイへ7スベーり型核燃料棒を提供りることに
ある。The purpose of the present invention is to -1 J, Umoto-(1η next technique ((・
The objective is to provide a highly safe 7-sphere nuclear fuel rod that eliminates the shortcomings of I, does not reduce the fuel pin spacing, is easy to manufacture and assemble, does not cause cladding wear, and is highly safe. .
かかる目的を達成しうる本発明は、スペーサワイヤと燃
料被覆管の材百1は同一成分のスリンレス鋼であるが、
スペーサライA7がt3!i l’l凍覆筑よりも小さ
い冷間加工度のものを用いたワイヤスペーサ型核燃γl
棒である。In the present invention, which can achieve such an object, the material of the spacer wire and the fuel cladding tube is made of sulinless steel of the same composition,
Spacerai A7 is t3! i l'l Wire spacer type nuclear fuel gamma l using a material with a degree of cold working smaller than that of frost-covered dust
It's a stick.
以下、本発明について更に詳しく説明する。The present invention will be explained in more detail below.
図面はワイA7スペーリ゛型核燃料棒の 例を示J−説
明図である。核燃料ビンは、従来同作、燃わ1被覆管1
内に核燃料ペレツ(〜2を積層% Ig L、/、両端
部を上部端栓3及び下部端栓4て密封した溝光である。The drawing is an explanatory diagram showing an example of a YA7 Spacey type nuclear fuel rod. The nuclear fuel bottle is the same as the conventional one, 1 burner 1 cladding tube 1
It is a groove light in which nuclear fuel pellets (~2% Ig L) are laminated inside, and both ends are sealed with an upper end plug 3 and a lower end plug 4.
なお、符号5 LJ核燃判ベレツ1〜2を押えるための
=1イルスプリンタである。燃ワ1ピンの外周にはワイ
ヤスベ−(ノロか巻回され、そのワイ1?によって燃f
′8+ピン間隔が保持される構j告である。本発明では
、上記燃オ81被覆篭1とスペーサライ176の(4買
は、同一成分のスリンレス鋼であるが、スペー1プワイ
\7Gか燃A”I ’a m宣1、よりも小さい冷間加
工度のものである。Note that the code 5 is a =1 irsprinter for holding down the LJ nuclear fuel type berets 1 and 2. A wire base is wound around the outer periphery of the 1st pin of the fuel, and the wire 1?
'8+ pin spacing is maintained. In the present invention, the spacer layer 176 and the spacer layer 176 are made of stainless steel with the same composition, but the spacer layer 81 coated basket 1 and the spacer layer 176 are made of stainless steel with the same composition, but the spacer layer 81 coated basket 1 and the spacer layer 176 are made of stainless steel with the same composition. It is highly processed.
ここて冷間加工度とは、加工前の+A H′!長さを1
0、加工後のtA材料長をLlどしたとさ、100x
(Ll −LO)/LO(%〕で定義されるmである。Here, the degree of cold work means +A H'! before processing. length 1
0, when the tA material length after processing is set to Ll, 100x
m is defined as (Ll - LO)/LO (%).
本発明において、燃料被覆色1としてに1、冷間1+t
lT度20%のS tJ S 31Gステンレス鋼を、
ワイヤスペーサ6どしてIJ、より冷間加工度の小さい
、例えば15%あるいは10%等の5US31Gステン
レス鋼、あるいは焼鈍処1」シた(冷間加工度O%の)
SUS31Gスアンレス鋼を用いることができる。S
U S 31Gの焼鈍熱処理の条1′Fとしてlよ、例
えば渇曵1000・〜1100”Cで数分程度である。In the present invention, fuel cladding color 1 is 1, cold 1+t
S tJ S 31G stainless steel with 1T degree of 20%,
The wire spacer 6 is made of IJ, 5US31G stainless steel with a lower degree of cold work, such as 15% or 10%, or annealed (with a degree of cold work of 0%).
SUS31G Suanless steel can be used. S
For example, the annealing heat treatment of US 31G is about several minutes at 1000 to 1100''C.
本発明に係る核燃料棒では、高速中性子の照剖吊が低い
時には、上記冷間加工度の相違によって、燃料被覆管1
の表面硬度がツ、イ〜7スベーサ6の表面硬度よりも高
くなり、そのtこめ、148体振動にj、って隣接ビン
のりイ■スペーサと接触18動しても摩耗現象は起こら
bい。また、祠オ′31は高速中性子で照QJされると
硬度が上背し、製造時の冷間加工刑こよらず一定値に収
束づ−る。In the nuclear fuel rod according to the present invention, when the optical suspension of fast neutrons is low, due to the difference in the degree of cold working, the fuel cladding tube
The surface hardness of the spacer 6 becomes higher than that of the spacer 6, and due to the vibration of the 148 body, no wear phenomenon occurs even if the adjacent bottle glue 18 moves in contact with the spacer. . Furthermore, when the shank 31 is irradiated with high-speed neutrons, its hardness increases and converges to a constant value regardless of the cold processing during manufacturing.
このため、燃(′31被覆管1とワーイl’スベーリ゛
Gとが同材質の場合は同−硬1食となるように変化し、
接触摺動による摩耗現象は、高)*中・11−子照θ1
邑の増加によって生じやり−い1頃向となる。For this reason, if the fuel ('31 cladding tube 1 and the wire material G are made of the same material), the same hardness will occur.
The wear phenomenon due to contact sliding is high)
Due to the increase in the number of villages, the number of villages will increase.
しかし、ワイヤスペーサ6の冷間加工度が燃料被覆管1
の冷間加工度より小さい本発明の核燃1131棒におい
ては、高速中性了照用による硬度増加と並行して材料に
スウェリングとクリープが牛じ、しかもぞれらの邑は冷
間加工度の小さいワイψスペーりの方が大きいため、ワ
イへ7か緩む現争が生じる。このため、被覆跨(こ当る
ライ1アの運動エネルギが小さくなり、かつ原子炉の運
転・停止に1二って接触位置が変化し、燃料Plrrl
管の肉厚損耗は逆行しない。覆なわら、燃料ビン破損に
至るような人さな減肉は生じないのである。However, the degree of cold working of the wire spacer 6 is
In the nuclear fuel 1131 rod of the present invention, which has a cold working degree smaller than that of Since the smaller wye ψ space is larger, a current dispute arises where the wye is 7 or less. For this reason, the kinetic energy of the lie 1a that hits the cladding becomes smaller, and the contact position changes as the reactor starts and stops, and the fuel Plrrl
The loss of pipe wall thickness will not reverse. However, there is no significant thinning that would lead to damage to the fuel bottle.
木5’l明は上記のように、スペーサライ)7が燃料被
覆管よりも小さい冷間加工度であるのζ′、初期におい
ては燃料被覆管がワイ′17スベーリ゛より表面硬度が
大きくなり、流体振動による燃料ビン同士の接触摺動に
起因する摩耗は燃′A:1被Wi管には生じないし、ま
た高速中性子に照!、!4さ机て′ノイA7スペー11
の硬度が被覆管の硬度に)丘づき、摩耗現象が生起づる
条件に近づいた場合は、同時にワイ′I7スペーサに生
じるスウェリングとクリープによってワイヤが緩み、摩
耗現象は起らないか、もしくは起っても初期の段階で停
止する。As mentioned above, the spacer line 7 has a smaller degree of cold working than the fuel cladding tube, and in the initial stage the fuel cladding tube has a surface hardness greater than that of the fuel cladding tube. Wear caused by contact sliding between fuel bottles due to fluid vibration does not occur in the fuel tube, and it is also susceptible to high-speed neutrons! ,! 4 desk te'noi A7 space 11
If the hardness of the cladding increases (the hardness of the cladding tube) and approaches the condition where a wear phenomenon occurs, the wire becomes loose due to the swelling and creep that occurs in the spacer, and the wear phenomenon may not occur or may occur. However, it stops at an early stage.
従って本発明にJ、れば、核燃i’1里合体を構成する
際、核燃料棒の間1;14は製造・111立が容易シ多
広い間隔でよく、安全四が高く、かつ製作〕1ストが高
くならない咳燃1′:1捧を提jj(てきるjlij
E2、極めてづぐれた効果をイ1りるらの(ある。Accordingly, according to the present invention, when constructing a nuclear fuel i'1 solution, the space between the nuclear fuel rods 1; 14 is easy to manufacture and erect, and wide spacing is sufficient, safety is high, and manufacturing is easy. I would like to propose a 1':1 ratio to prevent the strike from becoming too high.
E2, there is a very unusual effect.
図面は、ワイ\7スペーサ型核燃料棒の 例を承り説明
図である。
1・・・燃オ′31被覆質、2・・・核燃料ぺ17−J
1−13・・・土部端栓、4・・・下部端枠、5・・
・=1イル・スジリング、6・・・ワイA7スペー→〕
。
特許出願人 動力炉・核燃訓開発小業団代 理
人 尾 股 行 シ1)1同
茂 児 慎同
荒 本 友之助
499−The drawing is an explanatory diagram of an example of a Y\7 spacer type nuclear fuel rod. 1... Nuclear fuel '31 coating material, 2... Nuclear fuel P17-J
1-13... Soil end plug, 4... Lower end frame, 5...
・=1 Il Sujiring, 6...Y A7 space →]
. Patent applicant Representative of Power Reactor/Nuclear Fuel Training Development Small Business Group
Human tail crotch line 1) 1 same
Shindo Shigeji
Aramoto Tomonosuke499-
Claims (1)
された構造の核燃料棒にJ3いて、スベーリワイ\7と
燃料被覆管の(4買は同一成分のステンレス鋼であるが
、スベー4〕rノイ)7が燃オ′;1被覆管よりも小さ
い冷間j1[1工度のものであることを特徴とづるライ
1フスベーり型核燃利棒。 2、ステンレス鋼が5Us316スj−ンレス鋼である
特許請求の範囲第1項記載の核燃料棒。 3、燃料被覆管の冷間加工度が約20%であり、スペー
サワイへ7の冷間加工度が約15%である特許請求の範
囲第2項記載の核燃料棒。[Claims] 1. Wire 17 is installed in a nuclear fuel rod J3 having a structure in which it is wound around the outer periphery of a fuel pin using a spacer. However, a nuclear fuel rod of the life type nuclear fuel rod is characterized in that the fuel rod is of a cold working degree smaller than the combustion tube. 2. The nuclear fuel rod according to claim 1, wherein the stainless steel is 5Us316 stainless steel. 3. The nuclear fuel rod according to claim 2, wherein the degree of cold working of the fuel cladding tube is about 20%, and the degree of cold working of the spacer wire 7 is about 15%.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57134990A JPS5926091A (en) | 1982-08-02 | 1982-08-02 | Wire spacer type nuclear fuel rod |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57134990A JPS5926091A (en) | 1982-08-02 | 1982-08-02 | Wire spacer type nuclear fuel rod |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS5926091A true JPS5926091A (en) | 1984-02-10 |
Family
ID=15141353
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57134990A Pending JPS5926091A (en) | 1982-08-02 | 1982-08-02 | Wire spacer type nuclear fuel rod |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5926091A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2019529889A (en) * | 2016-09-05 | 2019-10-17 | ステート・アトミック・エナジー・コーポレーション・ロスアトム・オン・ビハーフ・オブ・ザ・ロシアン・フェデレーションState Atomic Energy Corporation ‘Rosatom’ On Behalf Of The Russian Federation | Fuel rod for fast neutron reactor |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50116899A (en) * | 1974-03-01 | 1975-09-12 |
-
1982
- 1982-08-02 JP JP57134990A patent/JPS5926091A/en active Pending
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50116899A (en) * | 1974-03-01 | 1975-09-12 |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2019529889A (en) * | 2016-09-05 | 2019-10-17 | ステート・アトミック・エナジー・コーポレーション・ロスアトム・オン・ビハーフ・オブ・ザ・ロシアン・フェデレーションState Atomic Energy Corporation ‘Rosatom’ On Behalf Of The Russian Federation | Fuel rod for fast neutron reactor |
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