JPS5849838B2 - fuel assembly - Google Patents

fuel assembly

Info

Publication number
JPS5849838B2
JPS5849838B2 JP54150157A JP15015779A JPS5849838B2 JP S5849838 B2 JPS5849838 B2 JP S5849838B2 JP 54150157 A JP54150157 A JP 54150157A JP 15015779 A JP15015779 A JP 15015779A JP S5849838 B2 JPS5849838 B2 JP S5849838B2
Authority
JP
Japan
Prior art keywords
fuel
cladding tube
cladding
channel box
copper
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
JP54150157A
Other languages
Japanese (ja)
Other versions
JPS5673386A (en
Inventor
利久 白川
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 JP54150157A priority Critical patent/JPS5849838B2/en
Publication of JPS5673386A publication Critical patent/JPS5673386A/en
Publication of JPS5849838B2 publication Critical patent/JPS5849838B2/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】 本発明は沸騰水形原子炉の燃料集合体に関する。[Detailed description of the invention] The present invention relates to a fuel assembly for a boiling water nuclear reactor.

一般に沸騰水形原子炉の燃料集合体はチャンネルボック
ス内に複数の燃料棒を収容して構成され、また各燃料棒
は被覆管内に燃料ペレットを収容した構造をなしている
In general, a fuel assembly for a boiling water nuclear reactor is constructed by housing a plurality of fuel rods in a channel box, and each fuel rod has a structure in which fuel pellets are housed in a cladding tube.

ところで、燃料ペレットの燃焼に伴って生成された核分
裂生成物たとえばよう素、セシウムあるいはよう素がベ
ータ崩壊して生成されたキセノン等は比重が大であるの
で被覆管の下部に溜る傾向がある。
Incidentally, nuclear fission products produced during the combustion of fuel pellets, such as iodine, cesium, or xenon produced by beta decay of iodine, have a high specific gravity and therefore tend to accumulate in the lower part of the cladding tube.

そしてこれら核***生成物等は熱伝導率が小さいので、
被覆管下部の燃料ペレットは上部の燃料ペレットに比べ
て放熱が悪く、温度が上昇する傾向にある。
And since these fission products have low thermal conductivity,
The fuel pellets at the bottom of the cladding have poor heat dissipation compared to the fuel pellets at the top, and their temperature tends to rise.

また、沸騰水形原子炉では冷却材中でボイドが生成され
、このボイドの分布は下方では粗、上方で密であるから
、上方では高速中性子が熱中性子に減速される割合が少
なく、よって燃料棒の上下方向の出力分布は上方で小、
下方で大となる傾向をもつ。
In addition, in a boiling water reactor, voids are generated in the coolant, and the distribution of these voids is coarse in the lower part and denser in the upper part.Therefore, the proportion of fast neutrons being decelerated into thermal neutrons in the upper part is small, and therefore the fuel The power distribution in the vertical direction of the rod is small at the top,
It tends to become larger in the downward direction.

したがって、これらの傾向が相乗的に作用して下方の燃
料ペレットは高温となり、膨張して被覆管に接触すると
ともに出力の上昇が急激におこなわれた場合には下方の
燃料ペレットが急に膨張して被覆管に激しく接触し、被
覆管を破損することがある等の不具合があった。
Therefore, these tendencies act synergistically, causing the lower fuel pellets to reach a high temperature, expand and contact the cladding tube, and if the output is suddenly increased, the lower fuel pellets will suddenly expand. There were problems such as violent contact with the cladding tube and damage to the cladding tube.

また、核***生成物中のよう素は化学的に活性が高く、
被覆管を腐食して被覆管の破損を招く要因となる等の不
具合があった。
In addition, iodine in fission products is highly chemically active;
There were problems such as corroding the cladding tube and causing damage to the cladding tube.

このような不具合を解消するため、被覆管の内面全体に
燃料ペレットに対する滑動性のよい銅等のバリャ材を被
覆し、燃料ペレットの急激な膨張による被覆管への激し
い接触を緩和し、またよう素等による被覆管の腐食を防
止して被覆管の破損を防止する試みがなされた。
In order to eliminate these problems, the entire inner surface of the cladding tube is coated with a barrier material such as copper that has good sliding properties against the fuel pellets, to alleviate the harsh contact with the cladding tube caused by the rapid expansion of the fuel pellets, and to Attempts have been made to prevent damage to the cladding tube by preventing corrosion of the cladding tube.

しかし、銅はその中性子吸収断面積が大きいため、この
ように被覆管に銅被覆を施すと中性子吸収が大きくなり
、燃料ペレットの燃焼度が低下し、燃料経済上きわめて
不利となる不具合があった。
However, since copper has a large neutron absorption cross-section, applying copper coating to the cladding tube increases neutron absorption, lowering the burnup of the fuel pellets, which is extremely disadvantageous in terms of fuel economy. .

本発明は以上の事情にもとづいてなされたもので、その
目的とするところは核***生成物等による被覆管下部の
破損を確実に防止して燃料の健全性を高め、かつ燃料ペ
レットの反応を阻害することなく燃料経済上の不利を招
くことのない燃料集合体を得ることにある。
The present invention has been made based on the above circumstances, and its purpose is to reliably prevent damage to the lower part of the cladding caused by nuclear fission products, improve the integrity of the fuel, and inhibit the reaction of fuel pellets. The object of the present invention is to obtain a fuel assembly that does not cause any disadvantages in terms of fuel economy.

以下本発明を図面に示す一実施例にしたがって説明する
The present invention will be explained below according to an embodiment shown in the drawings.

図中1は燃料集合体であって、この燃料集合体1は断面
略正方形のチャンネルボックス2内に複数の燃料棒3・
・・を8行8列に配置して構成されている。
In the figure, 1 is a fuel assembly, and this fuel assembly 1 has a plurality of fuel rods 3 and 3 inside a channel box 2 having a substantially square cross section.
... are arranged in 8 rows and 8 columns.

なお、4・・・は出力分布を調整するための水棒である
Note that 4... is a water rod for adjusting the output distribution.

そして、上記燃料棒3・・・は中性子吸収断面積の小さ
なジルコニウム合金等からなる被覆管5内に複数の短円
柱状をなす酸化ウラニウム等の燃料ペレット6・・・を
収容したものであって、これら燃料ペレット6・・・外
周面と被覆管5内周面との間には所定の間隙が形成され
ている。
The fuel rods 3 have a plurality of short cylindrical fuel pellets 6 made of uranium oxide or the like housed in a cladding tube 5 made of a zirconium alloy or the like having a small neutron absorption cross section. A predetermined gap is formed between the outer peripheral surface of these fuel pellets 6 and the inner peripheral surface of the cladding tube 5.

そして、この被覆管5の上端および下端には上部端栓7
および下部端栓8が溶接され、この被覆管5を封止して
いる。
Upper end plugs 7 are provided at the upper and lower ends of this cladding tube 5.
A lower end plug 8 is welded to seal the cladding tube 5.

なお、8は上部プレナム部である。In addition, 8 is an upper plenum part.

そして、この被覆管5内にはヘリウムガスが所定圧力で
加圧封入されている。
Helium gas is pressurized and sealed in the cladding tube 5 at a predetermined pressure.

そしてこれらの燃料棒3・・・は上端部および下端部を
上部タイプレート9および下部タイプレート10で支持
され、また中間部はスペーサ11によって支持され、上
部チャンネルボックス2内に互に間隙を存して所定の配
置で配列されている。
These fuel rods 3... are supported at their upper end and lower end by an upper tie plate 9 and a lower tie plate 10, and their intermediate parts are supported by a spacer 11, leaving a gap between them in the upper channel box 2. and are arranged in a predetermined arrangement.

そして、冷却材の軽水は上記チャンネルボックス2の下
部のノズル12からこのチャンネルボックス2内に流入
して上方に流れ、各燃料棒3・・・を冷却するように構
成されている。
Light water as a coolant flows into the channel box 2 from the nozzle 12 at the bottom of the channel box 2 and flows upward to cool each fuel rod 3 .

そして、上記の燃料棒3・・・のうちチャンネルボック
ス2の内周面に臨む燃料棒3・・・すなわち周辺部に位
置する燃料棒3・・・は、第3図ないし第5図に示す如
く被覆管5の中央部から下部にわたる全長のほぼ%の領
域の内面にバリャ材の被覆たとえば銅被覆13が施され
ている。
Among the above fuel rods 3, the fuel rods 3 facing the inner circumferential surface of the channel box 2, that is, the fuel rods 3 located at the periphery are shown in FIGS. 3 to 5. As shown, the inner surface of the cladding tube 5 is coated with a barrier material, for example, a copper coating 13, in an area corresponding to approximately % of the total length from the center to the lower part.

この銅被覆13は被覆管5の内部下面に銅を被着したの
ちこの被覆管5内に高温の水蒸気を流し、この銅被覆1
3と被覆管5内面との間に酸化膜を形成したものであり
、この酸化膜によって銅が被覆管5を構成するジルコニ
ウム合金内に拡散するのを防止するように構成されてい
る。
This copper coating 13 is made by depositing copper on the inner lower surface of the cladding tube 5, and then flowing high-temperature steam into the cladding tube 5.
3 and the inner surface of the cladding tube 5, and this oxide film is configured to prevent copper from diffusing into the zirconium alloy constituting the cladding tube 5.

なお、上記チャンネルボックス2内に臨む燃料棒3・・
・以外の燃料棒3・・・にはその被覆管5内面に銅被覆
は施されていない。
In addition, the fuel rod 3 facing inside the channel box 2...
The inner surface of the cladding tube 5 of the fuel rods 3 other than . is not coated with copper.

そして、このように構成された燃料集合体1は断面十字
形の制御棒14の周囲に4体づつ配置され、炉心を構成
するものである。
The fuel assemblies 1 thus constructed are arranged in groups of four around the control rods 14 each having a cross-shaped cross section to constitute a reactor core.

以上の如く構成された本発明の一実施例は燃料ペレット
6・・・の燃焼によって生成された核***生成物等は被
覆管5内に封じ込められ、外部に洩れることはない。
In one embodiment of the present invention constructed as described above, nuclear fission products and the like generated by combustion of the fuel pellets 6 are contained within the cladding tube 5 and do not leak to the outside.

そして、これら被覆管5内にはへリウムガスが封入され
ており、核***生成物等はこのヘリウムガスにより比重
が大であるから被覆管の下部に溜る。
These cladding tubes 5 are filled with helium gas, and nuclear fission products and the like have a high specific gravity due to the helium gas, so they accumulate in the lower part of the cladding tubes.

そして、ヘリウムガスはその熱伝導係数が4 0 sm
’CrrLt. sec ”deg ’であるのに対し
て核***生成物はその熱伝導係数が数十cal−cm
’ ・sec ’ ・deg ”程度のものであるから
下部の燃料ペレット6・・・は放熱が悪く、また前述の
如く沸騰水形原子炉では炉心下部で熱中性子束密度が高
くなる傾向があるので、下部の燃料ペレット6・・・の
反応が大きく、高温に加熱される傾向がある。
And helium gas has a thermal conductivity coefficient of 40 sm
'CrrLt. sec ``deg'', whereas the thermal conductivity of fission products is several tens of cal-cm.
' ・sec '・deg'', the lower fuel pellet 6... has poor heat dissipation, and as mentioned above, thermal neutron flux density tends to be high in the lower part of the core in boiling water reactors. , the lower fuel pellets 6... tend to undergo a large reaction and be heated to a high temperature.

しかし、この一実施例のものは被覆管5の下部のみに銅
被覆13が施されているのでこの銅被覆13によって中
性子が吸収され、上記の傾向を相殺するので燃料棒3・
・・の上下方向の出力分布は均一となり、下部の燃料ペ
レット6・・・が過熱されるようなことはなく、この下
部の燃料ペレット6・・・の急激な膨張等による被覆管
5の破損を生じるようなことはない。
However, in this embodiment, since the copper coating 13 is applied only to the lower part of the cladding tube 5, neutrons are absorbed by the copper coating 13, which offsets the above-mentioned tendency.
The power distribution in the vertical direction of ... will be uniform, and the lower fuel pellets 6 will not be overheated, and the cladding tube 5 will be damaged due to rapid expansion of the lower fuel pellets 6. There is no possibility that this will occur.

また、この銅被覆13は被覆管5の下部に溜った核***
生成物のよう素等による被覆管5の腐食を肪止する。
Further, this copper coating 13 prevents corrosion of the cladding tube 5 due to iodine, etc., a fission product accumulated in the lower part of the cladding tube 5.

また、この銅被覆13は被覆管5下部の必要な部分のみ
に施されているから、反応度の低下は少なく、燃料経済
上の不利を招くこともない。
Furthermore, since the copper coating 13 is applied only to the necessary portion of the lower part of the cladding tube 5, the reactivity is less reduced and there is no disadvantage in terms of fuel economy.

また、この銅被覆13を施した燃料棒3・・・はチャン
ネルボックス2内面に臨む位置にのみ設けたので、全体
の反応度低下がきわめて少なく、燃料経済上きわめて有
利であり、かつ被覆管5の破損等も確実に防止できる。
In addition, since the fuel rods 3 coated with the copper cladding 13 are provided only at positions facing the inner surface of the channel box 2, the overall reactivity decrease is extremely small, which is extremely advantageous in terms of fuel economy. damage etc. can be reliably prevented.

すなわち、燃料棒3・・・の平均線出力密度は第6図に
示す如く制御棒14を挿入した場合と第7図に示す如く
制御棒14を引抜いた場合とでは異なり、この平均線出
力密度の差は制御棒14に最も近い燃料棒3・・・すな
わちチャンネルボックス2の内面に臨む位置にある燃料
棒3・・・できわめて太き<8kW/ftもの差が生じ
、これらチャンネルボックス2の内面に臨む燃料棒3・
・・がその被覆管5の破損を生じやすいものである。
That is, the average linear power density of the fuel rods 3... is different when the control rod 14 is inserted as shown in FIG. 6 and when the control rod 14 is withdrawn as shown in FIG. The difference in thickness is extremely large at the fuel rods 3 closest to the control rods 14, that is, the fuel rods 3 facing the inner surface of the channel box 2, and a difference of <8 kW/ft occurs between these channel boxes 2. Fuel rod facing the inner surface 3.
... is likely to cause damage to the cladding tube 5.

したがってこの被覆管5の破損が生じる可能性の大きな
燃料棒3・・・についてのみ銅被覆13を施すことによ
って被覆管5の破損が防止でき、かつ燃料集合体1全体
の反応度の低下を最少にとどめることができるものであ
る。
Therefore, by applying the copper cladding 13 only to the fuel rods 3 where there is a high possibility that the cladding tube 5 will be damaged, damage to the cladding tube 5 can be prevented, and the decrease in the reactivity of the entire fuel assembly 1 can be minimized. It is something that can be kept within.

なお、本発明は上記の一実施例には限定されず、たとえ
ば銅被覆を施す燃料棒はチャンネルボックスの内面に臨
む周辺部の燃料棒のみに限らず、必要に応じて他の燃料
棒の被覆管の下部内面に銅被覆を施してもよい。
Note that the present invention is not limited to the above-mentioned embodiment; for example, the fuel rods to be coated with copper are not limited to only the fuel rods in the peripheral area facing the inner surface of the channel box, but may be coated on other fuel rods as necessary. A copper coating may be applied to the lower inner surface of the tube.

また、銅被覆はニオブ、スズ、マグネシウム、カルシウ
ム、クロム、鉄、チタン、亜鉛、モリブデン、ジルコニ
ウム、アルミニウムなどから選らばれた少なくとも1種
からなる材料で置換することができる。
Further, the copper coating can be replaced with a material consisting of at least one selected from niobium, tin, magnesium, calcium, chromium, iron, titanium, zinc, molybdenum, zirconium, aluminum, and the like.

上述の如く本発明は燃料棒の被覆管の下半分の内面のみ
にバリャ材を被覆したものである。
As described above, in the present invention, only the inner surface of the lower half of the cladding tube of the fuel rod is coated with a barrier material.

したがってこのバリャ材の被覆によって中性子が吸収さ
れ下部の燃料ペレットが上部の燃料ペレットより反応度
が高くなり過熱される傾向が相殺されて燃料棒の上下方
向の出力分布が均一化され、燃料の健全性が向上される
とともにこのバリャ材の被覆によって燃料ペレットの膨
張による被覆管の破損や被覆管下部に溜る核***生成物
等による被覆管の腐食が防止され、かつこのバリャ材の
被覆は被覆管の下部のみに施されているものであるから
燃料集合体全体としての反応度の低下が少なく、燃料経
済上の不利を招くことがない等その効果は大である。
Therefore, the barrier material coating absorbs neutrons, making the lower fuel pellets more reactive than the upper fuel pellets, canceling out the tendency to overheat, equalizing the power distribution in the vertical direction of the fuel rod, and improving the health of the fuel. In addition to improving the properties of the cladding, the coating with this barrier material prevents damage to the cladding due to the expansion of fuel pellets and corrosion of the cladding due to fission products that accumulate at the bottom of the cladding. Since it is applied only to the lower part, the reactivity of the fuel assembly as a whole does not decrease much, and its effects are great, such as not causing any disadvantages in terms of fuel economy.

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

図面は本発明の一実施例を示し、第1図は斜視図、第2
図は横断面図、第3図は燃料棒の縦断面図、第4図は第
3図のIV−IV線に沿う断面図、第5図は第3図のv
−V線に沿う断面図、第6図および第7図は燃料棒の平
均線出力を示す概略図である。 1・・・・・・燃料集合体、2・・・・・・チャンネル
ボックス、3・・・・・・燃料棒、5・・・・・・被覆
管、6・・・・・・燃料ペレット、13・・・・・・銅
被覆(バリャ被覆材)、14・・・・・・制御棒。
The drawings show one embodiment of the present invention, with the first figure being a perspective view and the second figure being a perspective view.
The figure is a cross-sectional view, Figure 3 is a vertical cross-sectional view of the fuel rod, Figure 4 is a cross-sectional view taken along line IV-IV in Figure 3, and Figure 5 is a v
6 and 7 are schematic diagrams showing the average linear output of the fuel rods. 1...Fuel assembly, 2...Channel box, 3...Fuel rod, 5...Claying tube, 6...Fuel pellet , 13... Copper coating (barrier coating material), 14... Control rod.

Claims (1)

【特許請求の範囲】 1 被覆管内に燃料ペレットを収容した複数の燃料棒を
チャンネルボックス内に収容したものにおいて、上記被
覆管内にヘリウムガスを加圧封入するとともに上記被覆
管のほぼ中央部から下部にわたるほぼHの領域内面のみ
にバリャ被覆材を被覆したことを特徴とする燃料集合体
。 2 前記被覆管の下部内面にバリャ被覆材を被覆した燃
料棒は前記チャンネルボックスの内周面に臨む周辺部の
みに配置されていることを特徴とする前記特許請求の範
囲第1項記載の燃料集合体。 3 バリャ被覆材としては銅、ニオブ、スス、マグネシ
ウム、カルシウム、クロム、鉄、チタン、亜鉛、モリブ
デン、ジルコニウム、アルミニウムから選らばれた少な
くとも1種からなる材料で構成されたことを特徴とする
特許請求の範囲第1項または第2項記載の燃料集合供
[Scope of Claims] 1. A channel box in which a plurality of fuel rods each containing fuel pellets are housed in a cladding tube, in which helium gas is pressurized and sealed in the cladding tube, and helium gas is sealed in the cladding tube from approximately the center to the lower part of the cladding tube. 1. A fuel assembly characterized in that only the inner surface of an approximately H area extending over the area is coated with a barrier coating material. 2. The fuel according to claim 1, wherein the fuel rods whose lower inner surface of the cladding tube is coated with a barrier coating material are arranged only in the peripheral portion facing the inner circumferential surface of the channel box. Aggregation. 3. A patent claim characterized in that the barrier coating material is made of at least one material selected from copper, niobium, soot, magnesium, calcium, chromium, iron, titanium, zinc, molybdenum, zirconium, and aluminum. The fuel assembly supply described in paragraph 1 or 2 of the scope
JP54150157A 1979-11-20 1979-11-20 fuel assembly Expired JPS5849838B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP54150157A JPS5849838B2 (en) 1979-11-20 1979-11-20 fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP54150157A JPS5849838B2 (en) 1979-11-20 1979-11-20 fuel assembly

Publications (2)

Publication Number Publication Date
JPS5673386A JPS5673386A (en) 1981-06-18
JPS5849838B2 true JPS5849838B2 (en) 1983-11-07

Family

ID=15490741

Family Applications (1)

Application Number Title Priority Date Filing Date
JP54150157A Expired JPS5849838B2 (en) 1979-11-20 1979-11-20 fuel assembly

Country Status (1)

Country Link
JP (1) JPS5849838B2 (en)

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JPS5824888A (en) * 1981-08-07 1983-02-14 株式会社日立製作所 Nuclear fuel assembly
US20140169516A1 (en) * 2012-12-14 2014-06-19 Global Nuclear Fuel - Americas, Llc Fuel rods with varying axial characteristics and nuclear fuel assemblies including the same

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