JPS5880593A - Nuclear fuel element - Google Patents

Nuclear fuel element

Info

Publication number
JPS5880593A
JPS5880593A JP56178388A JP17838881A JPS5880593A JP S5880593 A JPS5880593 A JP S5880593A JP 56178388 A JP56178388 A JP 56178388A JP 17838881 A JP17838881 A JP 17838881A JP S5880593 A JPS5880593 A JP S5880593A
Authority
JP
Japan
Prior art keywords
fuel
nuclear fuel
hollow
fuel element
nuclear
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
Application number
JP56178388A
Other languages
Japanese (ja)
Inventor
中井 敬一
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.)
Hitachi Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
Hitachi 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 Hitachi Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP56178388A priority Critical patent/JPS5880593A/en
Publication of JPS5880593A publication Critical patent/JPS5880593A/en
Pending 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】 本発明は、核燃料要素に係り、特に燃料体として中空燃
料ペレットを装填した核燃料要素に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fuel element, and more particularly to a nuclear fuel element loaded with hollow fuel pellets as a fuel body.

沸騰水型原子炉等のように冷却材として流体を使用して
いる原子炉の燃料は、一般にm1図に示すような核燃料
要素が便用さ扛ている。すなわち、細径で円筒状の金属
被横管1に、二酸化ウランや二歌化プルトニウムの粉末
をペレット状に貌結した燃料ペレット2を装填し、燃料
ペレット2を適切な力で押えるためのスプリング3を挿
入後、熱伝導率の良好なガスを封入して、両端を端栓4
で密封した構造である。
Nuclear fuel elements such as those shown in the m1 diagram are generally used as fuel for nuclear reactors such as boiling water reactors that use fluid as a coolant. That is, a small-diameter, cylindrical metal sheathed tube 1 is loaded with fuel pellets 2 in which uranium dioxide or plutonium dioxide powder is formed into pellets, and a spring is used to press down the fuel pellets 2 with an appropriate force. After inserting 3, fill in gas with good thermal conductivity and plug both ends with end plug 4.
It has a sealed structure.

このような核燃料要素では、原子炉の通常運転時に燃料
ペレット2は中心部で1800C以上の高°温となると
ともに、中心部と表面部で12000近い温度勾配を生
じる。このため、燃料ペレット2は中心部と表面部で熱
膨張に差が生じ、第2図に示すように、つづみ形に熱変
形すると同時に、熱応力によって多数の割れを生じる。
In such a nuclear fuel element, during normal operation of the nuclear reactor, the fuel pellet 2 reaches a high temperature of 1,800° C. or more at the center, and a temperature gradient of nearly 12,000° C. occurs between the center and the surface. For this reason, the fuel pellet 2 has a difference in thermal expansion between the center and the surface, and as shown in FIG. 2, the fuel pellet 2 is thermally deformed into a chain shape and at the same time, a large number of cracks occur due to thermal stress.

そして燃料ペレット2の最も熱変形の大きなリッジ部5
が、被覆管lと強い接触を起こす。このような燃料ペレ
ット2と被覆管lの機械的な相互作業をPCIといい、
このPCIは、被覆管1に局部的な応力果中や歪集中を
生じさせ、核燃料要素が破損する危険性がおる。
The ridge portion 5 of the fuel pellet 2 has the largest thermal deformation.
causes strong contact with the cladding tube l. This mechanical interaction between the fuel pellets 2 and the cladding tube 1 is called PCI.
This PCI causes local stress effects and strain concentration in the cladding tube 1, and there is a risk that the nuclear fuel element will be damaged.

第3図に前記燃料ペレット2の代わりに中空燃料ベレッ
ト6を装填した核燃料要素を示す。
FIG. 3 shows a nuclear fuel element loaded with hollow fuel pellets 6 instead of the fuel pellets 2 described above.

中空燃料ベレット6は、核燃料要素単位長さ当りの熱出
力を下けることなく、燃料温度を低下させることができ
る。従って、中空燃料ペレット6を用いることは、前記
の熱変形量を小さくできるだけでなく、燃料ペレットか
ら放出される核分裂生成ガスを少なくできる等、多くの
利点を有している。
The hollow fuel pellet 6 can reduce the fuel temperature without reducing the heat output per unit length of the nuclear fuel element. Therefore, using the hollow fuel pellet 6 has many advantages, such as not only being able to reduce the amount of thermal deformation described above, but also being able to reduce the fission product gas released from the fuel pellet.

このように多くの利点を有する中“空燃料ペレット6は
以下ρような欠点があった。
Although the hollow fuel pellet 6 has many advantages as described above, it has the following drawbacks.

第1点は、中心孔7内の製造時封入ガスや核分裂生成ガ
スが高温になるため、核燃料要素の内圧が高くなる危険
性である。これはPCI等によって生じる被覆管1の引
張応力を増大させることになり、核燃料要素の乙全性上
好ましくない。
The first point is that there is a risk that the internal pressure of the nuclear fuel element will increase because the gas sealed in the center hole 7 during production and the gas produced by nuclear fission become high temperatures. This increases the tensile stress of the cladding tube 1 caused by PCI and the like, which is unfavorable in terms of the integrity of the nuclear fuel element.

第2点は、温度勾配によって生じる熱応力により割れた
燃料ペレット破片8が中心孔7に脱落することである。
The second point is that the broken fuel pellet fragments 8 fall into the center hole 7 due to thermal stress caused by the temperature gradient.

これは、核燃料要素の一方同で核燃料物質が不均一にな
るため、原子炉の運転特性に大きな影*’it及ぼす恐
れがある。
This may have a large impact on the operating characteristics of the nuclear reactor, as the nuclear fuel material becomes non-uniform on one side of the nuclear fuel element.

本発明の目的は、核燃料要素の内圧を低下させて被覆管
に生じる引張応力を減少させると同時に、燃料ペレット
破片の中心孔への脱落を防ぐ恢侮ヲ備えた中空燃料ペレ
ット型核燃料要素を提供することにある。
An object of the present invention is to provide a hollow fuel pellet-type nuclear fuel element that reduces the internal pressure of the nuclear fuel element to reduce the tensile stress generated in the cladding tube, and at the same time prevents fuel pellet fragments from falling into the central hole. It's about doing.

本発明は、中空燃料ベレットを装填して使用する核燃料
JIi索において、破も温度の高くなる中心孔より初期
封入ガスや核分裂生成ガスを排除することにより、核燃
料要素の内圧上昇を抑えて、被覆管に生じる引加応力を
減少させると同時に、燃料ペレット破片の中心孔への脱
at防ぐ手段として、中空燃料ペレットの中心孔内に円
柱体を設けたものである。
The present invention suppresses the increase in the internal pressure of the nuclear fuel element and eliminates the initially sealed gas and fission product gas from the center hole, where the temperature increases even when the rupture occurs, in a nuclear fuel JIi cable loaded with hollow fuel pellets. A cylindrical body is provided in the center hole of the hollow fuel pellet as a means for reducing the applied stress generated in the tube and at the same time preventing fuel pellet fragments from falling into the center hole.

本発明の実施例では、那騰水型原子炉で使用する核燃料
要素を対象に述べる。
In the embodiments of the present invention, nuclear fuel elements used in Nateng water reactors will be described.

第4図に本発明を具体化した場−合の核燃料要素の構造
を示す。すなわち、被覆管1に俵数の中空燃料ペレット
6を装填し、中′窒燃料ペレット6を適切な力で押える
ためのスプリング3を挿入後、両端を嬬栓4で密封した
核燃料要素において、中    □全燃料ペレット6の
中心孔71・Jに、本発明の円柱体9を設けた偽造であ
る。                )円柱体9に要
求される条件は以下のとおシである。
FIG. 4 shows the structure of a nuclear fuel element in which the present invention is embodied. That is, after loading several bales of hollow fuel pellets 6 into a cladding tube 1 and inserting a spring 3 to press down the hollow nitrogen fuel pellets 6 with an appropriate force, the hollow fuel element is sealed at both ends with plugs 4. □This is a counterfeit product in which the cylindrical body 9 of the present invention is provided in the center hole 71/J of all the fuel pellets 6. ) The conditions required for the cylindrical body 9 are as follows.

(11#&点が核燃料要素の最高温度に対して充分高い
こと。
(11# & point is sufficiently high compared to the maximum temperature of the nuclear fuel element.

(2)熱膨張率が中空燃料ペレットと同等、またはそれ
以下であること。
(2) The coefficient of thermal expansion is equal to or lower than that of hollow fuel pellets.

(3)  中性子経済の観点から中性゛子吸°収晧面槓
が小さいこと。
(3) From the perspective of neutron economy, the neutron absorption depth should be small.

まず、上記(])の融点について検討する。中空燃料ペ
レツ小は、その中空径を大きくするほど中心部の温度を
低下させることができるが、核燃料物質の重量減少をと
もなうため実用的にその中空径を燃料ペレット外径の3
0%程度とすることが望ましい。この場合、中心部の温
度は約1400Cになると予想される。従って、円柱体
の融点は1500C以上であることが心安である。(2
)の熱膨張率については、中空燃料ペレットと同等また
はそれ以下という条件を満足しない場合、円柱庫により
中空燃料ペレットは外に押ひろげられ、 PCIが増大
する危険性を生じることになる。
First, the melting point of (]) above will be discussed. For small hollow fuel pellets, the temperature at the center can be lowered by increasing the hollow diameter, but since this involves a reduction in the weight of the nuclear fuel material, it is practical to set the hollow diameter to 3 times the outer diameter of the fuel pellet.
It is desirable to set it to about 0%. In this case, the temperature at the center is expected to be approximately 1400C. Therefore, it is safe that the melting point of the cylindrical body is 1500C or higher. (2
), if the condition is not satisfied that the coefficient of thermal expansion is equal to or lower than that of the hollow fuel pellets, the hollow fuel pellets will be pushed outward by the cylindrical chamber, creating a risk of increased PCI.

この(1)、 (2)の条件を満足し、(3)の中性子
経済全考慰に入れると、円柱体の材質として二酸化ジル
コニウム(ZrO□)等が適している。
If conditions (1) and (2) are satisfied, and considering the neutron economy in (3), zirconium dioxide (ZrO□) or the like is suitable as the material for the cylinder.

本発明の一実施例によれは、第3図に示した中空燃料ベ
レット型核燃料要素において、蚊も高温となる中心孔7
から初期封入ガスや核分裂生成ガスを排除できるため、
核燃料要素の内圧を第5図に示したように低下させられ
るため、被覆管1に生じる引加応力を減少できる効果が
あり、さらに、燃料ペレット破片片8の中心孔7への脱
落を防止できる効果も備えている。
According to an embodiment of the present invention, in the hollow fuel pellet type nuclear fuel element shown in FIG.
Since the initial filler gas and fission product gas can be removed from the
Since the internal pressure of the nuclear fuel element can be lowered as shown in FIG. 5, it has the effect of reducing the stress applied to the cladding tube 1, and furthermore, it is possible to prevent fuel pellet fragments 8 from falling into the center hole 7. It also has effects.

前記発明の変形νりとして、円柱体のかわりに上下th
封した円筒管を用いることが可能である。
As a modification ν of the above invention, upper and lower th are used instead of the cylindrical body.
It is possible to use a sealed cylindrical tube.

この場合、中性子の経済性を向上させるという点で幼米
がある。
In this case, there is an advantage in terms of improving the economics of neutrons.

本発明によれば、中空燃料ペレット型核燃料要素にセい
て、核燃料要素の内圧全低下させると同  ・時に、燃
料ペレット破片の中心孔への脱落を防ぐことができる。
According to the present invention, in a hollow fuel pellet type nuclear fuel element, it is possible to completely reduce the internal pressure of the nuclear fuel element and at the same time prevent fuel pellet fragments from falling into the center hole.

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

第1図は従来反用されている中実燃料ペレットを用いた
核燃料要素の製造状恕における縦断面図、第2図は従来
便用されている中実燃料ペレツi用いた核燃料要素の変
形した状態における局部縦断面図、第3図は中天燃料ペ
レットのかわりに中空燃料ペレットを用いた核燃料要素
の縦断面図、第4図は本発明の一実施例である核燃料要
素の縦断面図、第5図は本発明と従来技術での核燃料要
素内圧の比較図である。 1・・・被覆管、2・・・燃料ペレット、3・・・スプ
リング、4・、・・端栓、°5・・・リッジ部、6・・
・中空燃料ペレット、′jF l 図 v−2図 477− 第 :3 躬 i!+  図 Y5図 WjjLll tetwet/l)
Figure 1 is a vertical cross-sectional view of a nuclear fuel element manufactured using conventionally used solid fuel pellets, and Figure 2 is a modified view of a nuclear fuel element using conventionally used solid fuel pellets. 3 is a longitudinal sectional view of a nuclear fuel element using hollow fuel pellets instead of solid fuel pellets; FIG. 4 is a longitudinal sectional view of a nuclear fuel element according to an embodiment of the present invention; FIG. 5 is a comparison diagram of the internal pressure of a nuclear fuel element according to the present invention and the prior art. DESCRIPTION OF SYMBOLS 1...Claying tube, 2...Fuel pellet, 3...Spring, 4...End plug, °5...Ridge part, 6...
・Hollow fuel pellet, 'jF l Figure v-2 Figure 477- No. 3 謬i! + Figure Y5 Figure WjjLll tetwet/l)

Claims (1)

【特許請求の範囲】[Claims] 1、両鴻モ端栓で密封した被覆管と、前記被覆管内に装
填された複数の中空燃料ペレットからなる核燃料要素に
おいて、前記中空燃料ペレットの中心孔部内に、円柱体
を設けたことを%徴とする核燃料要素。
1. In a nuclear fuel element consisting of a cladding tube sealed with both end plugs and a plurality of hollow fuel pellets loaded into the cladding tube, a cylindrical body is provided in the center hole of the hollow fuel pellet. Nuclear fuel elements.
JP56178388A 1981-11-09 1981-11-09 Nuclear fuel element Pending JPS5880593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56178388A JPS5880593A (en) 1981-11-09 1981-11-09 Nuclear fuel element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56178388A JPS5880593A (en) 1981-11-09 1981-11-09 Nuclear fuel element

Publications (1)

Publication Number Publication Date
JPS5880593A true JPS5880593A (en) 1983-05-14

Family

ID=16047615

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56178388A Pending JPS5880593A (en) 1981-11-09 1981-11-09 Nuclear fuel element

Country Status (1)

Country Link
JP (1) JPS5880593A (en)

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