JPH0540186A - Nuclear fuel element - Google Patents

Nuclear fuel element

Info

Publication number
JPH0540186A
JPH0540186A JP2405135A JP40513590A JPH0540186A JP H0540186 A JPH0540186 A JP H0540186A JP 2405135 A JP2405135 A JP 2405135A JP 40513590 A JP40513590 A JP 40513590A JP H0540186 A JPH0540186 A JP H0540186A
Authority
JP
Japan
Prior art keywords
nuclear fuel
fuel element
cladding tube
hydrogen
clad
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
JP2405135A
Other languages
Japanese (ja)
Inventor
Tadahiko Torimaru
忠彦 鳥丸
Masafumi Nakatsuka
雅文 中司
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.)
Nippon Nuclear Fuel Development Co Ltd
Original Assignee
Nippon Nuclear Fuel Development 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 Nippon Nuclear Fuel Development Co Ltd filed Critical Nippon Nuclear Fuel Development Co Ltd
Priority to JP2405135A priority Critical patent/JPH0540186A/en
Publication of JPH0540186A publication Critical patent/JPH0540186A/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

PURPOSE:To obtain a nuclear fuel element capable of preventing stress corrosion cracking of nuclear fuel clad and hydrogen embrittlement even in the case of clad rupture. CONSTITUTION:Between fuel pellets 1 in a fuel clad 4, a mixture of burnable poison (Gd, etc.) and a good hydrogen absorption material (Zr, etc.) which is coated with material 3 with good hydrogen permeability and combined in one, is provided in a fuel element. Thus, during a reactor power escalation, the local stress concentration in a clad is mitigated. Furthermore, even in the case of clad rupture, the hydrogen embrittlement can be prevented.

Description

【発明の詳細な説明】Detailed Description of the Invention

【産業上の利用分野】本発明は、原子炉で用いられる核
燃料要素に係り、特にその被覆管の内部を改善し、信頼
性を向上させた核燃料要素に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear fuel element used in a nuclear reactor, and more particularly to a nuclear fuel element having an improved cladding tube for improved reliability.

【0001】[0001]

【従来の技術】核燃料要素は、燃料被覆管内に複数個の
核燃料ペレットを積層収容し、上端部にガス溜用プレナ
ム部と核燃料ペレットを安定に支持するためのプレナム
スプリングを有し、両端開口部を上部および下部端栓で
密封溶接した構造となっている。以上の構成において、
被覆管には、核燃料ペレットから放出される放射性核分
裂生成物が管外周部の冷却材中に混入するのを防止する
ため、当該放射性核分裂生成物が外部に漏洩するのを阻
止する機能が求められているが、現在までの運転経験に
よれば、燃料の燃焼度が高くなった段階で出力が急激に
上昇すると、被覆管と腐食性核分裂生成物との化学反応
が起こり、また核燃料ペレットが熱膨張することによっ
てペレット両端面部が所所節状に変形するいわゆるリッ
ジ変形によって被覆管に応力が加わり、上記両者の重畳
作用により、被覆管に応力腐食割れを生じる恐れのある
ことが判明した。
2. Description of the Related Art A nuclear fuel element has a fuel cladding tube in which a plurality of nuclear fuel pellets are stacked and housed, and a plenum portion for gas storage and a plenum spring for stably supporting the nuclear fuel pellet are provided at an upper end portion, and both end opening portions are provided. It has a structure in which the upper and lower end plugs are hermetically welded. In the above configuration,
In order to prevent the radioactive fission products emitted from the nuclear fuel pellets from mixing into the coolant around the outer circumference of the cladding, the cladding tube is required to have a function to prevent the radioactive fission products from leaking to the outside. However, according to the operation experience to date, if the output suddenly rises when the burnup of the fuel becomes high, a chemical reaction occurs between the cladding and corrosive fission products, and the nuclear fuel pellets become hot. It has been found that stress is applied to the cladding tube by so-called ridge deformation in which both end surface portions of the pellet are deformed in a localized manner due to expansion, and the stress corrosion cracking may occur in the cladding tube due to the overlapping action of the both.

【0002】しかして、上記のごとき被覆管の応力腐食
割れを防止することを目的として、被覆管の内周面に例
えば厚さ80〜100μmの純ジルコニウムライナ層を
障壁として張設した、いわゆるジルコニウムライナ管が
特開昭55−164396号公報として提案されてお
り、上記ジルコニウムライナ管によって被覆管と腐食性
核分裂生成物との接触を防止するとともに、被覆管に発
生する局所応力を緩和して、当該被覆管の応力腐食割れ
を防止する効果が期待されている。
For the purpose of preventing the stress corrosion cracking of the cladding tube as described above, a so-called zirconium, for example, having a pure zirconium liner layer having a thickness of 80 to 100 μm stretched as a barrier on the inner peripheral surface of the cladding tube is used. A liner tube has been proposed as JP-A-55-164396, and the zirconium liner tube prevents contact between the cladding tube and corrosive fission products and relaxes local stress generated in the cladding tube. The effect of preventing stress corrosion cracking of the cladding tube is expected.

【0003】また実開昭55−55796号公報に示さ
れるように、燃料ペレットの端面部の出力をペレット腹
部より小さくし、燃料ペレットの熱応力によって生じる
リッジ変形を小さくして、被覆管との相互作用を弱める
ようにした核燃料要素が提案されている。さらに、上記
のリッジ変形を低減させる目的で、燃料ペレット内に可
塑性介在物質を挿入する提案が特開昭55−12819
3号公報に提案されている。
As disclosed in Japanese Utility Model Laid-Open No. 55-55796, the output of the end surface of the fuel pellet is made smaller than that of the pellet abdomen, and the ridge deformation caused by the thermal stress of the fuel pellet is made small so that the cladding tube Nuclear fuel elements have been proposed that have weakened interactions. Further, there is a proposal to insert a plastic interposition material in the fuel pellet for the purpose of reducing the above-mentioned ridge deformation.
It is proposed in Japanese Patent No.

【0004】[0004]

【発明が解決しようとする課題】しかしながら、従来の
技術によって製造した核燃料要素においては、燃料ペレ
ットの熱出力に分布を与えるようなものを製造すること
は、製造コスト面では不利である。また何らかの原因で
被覆管が破損して冷却水が被覆管内に浸入すると、直ち
に燃料が酸化されて水素が生成される。この水素がジル
コニウム合金からなる被覆管材内に拡散してゆき、水素
化物の形成と水素脆化を起す懸念があった。
However, in the nuclear fuel element manufactured by the conventional technique, it is disadvantageous in terms of manufacturing cost to manufacture a nuclear fuel element which gives a distribution to the heat output of the fuel pellets. Further, when the cladding tube is damaged for some reason and the cooling water enters the cladding tube, the fuel is immediately oxidized and hydrogen is generated. There is a concern that this hydrogen will diffuse into the coated pipe material made of a zirconium alloy, causing hydride formation and hydrogen embrittlement.

【0005】本発明は、上記の状況に鑑みてなされたも
ので、核燃料被覆管にリッジと称する局部応力集中が生
じにくく、したがって被覆管に応力腐食割れが生じない
と同時に、何らかの原因で被覆管が破損した場合にも、
被覆管の水素脆化を防止できるような信頼性の高い核燃
料要素を提供することを目的とする。
The present invention has been made in view of the above circumstances, and local stress concentration called a ridge is less likely to occur in a nuclear fuel cladding tube, so that stress corrosion cracking does not occur in the cladding tube, and at the same time, the cladding tube is caused for some reason. Even if the
An object is to provide a highly reliable nuclear fuel element capable of preventing hydrogen embrittlement of a cladding tube.

【0006】[0006]

【課題を解決するための手段】上記課題を解決するため
の本発明に係る核燃料要素の構成は、ジルコニウム合金
からなる燃料被覆管の内部に複数個の核燃料ペレットを
積層して収納し、上下の両端栓を密封してなる核燃料要
素において、可燃性毒物と水素吸収性のよい物質を、水
素透過性のよい被膜で被覆して一体化し、前記核燃料ペ
レット間に配設するようにしたことである。
The structure of a nuclear fuel element according to the present invention for solving the above-mentioned problems is such that a plurality of nuclear fuel pellets are stacked and housed inside a fuel cladding tube made of a zirconium alloy. In a nuclear fuel element in which both end plugs are sealed, a combustible poison and a substance having a good hydrogen absorbing property are covered with a film having a good hydrogen permeable property so as to be integrated and arranged between the nuclear fuel pellets. .

【0007】[0007]

【作用】核燃料要素において、燃料ペレットの端面部近
傍の熱出力を制限するためにガドリニウム(Gd)が有
効なことは公知であったが、その配置方法に技術的な課
題が残されていた。
In the nuclear fuel element, it was known that gadolinium (Gd) is effective for limiting the heat output in the vicinity of the end face portion of the fuel pellet, but there was a technical problem in the arrangement method.

【0008】本発明者らは、上記のGdの配置方法につ
いて、水素吸収手段と合わせて一体化成型することを考
え、また製造上の合理化をも検討した。すなわち、被覆
管が何らかの原因で破損した場合には、高温の燃料ペレ
ットは、浸入した冷却水によって酸化され、その結果水
素が発生し、被覆管内は、水蒸気とともに水素濃度が増
大する。
The present inventors considered the above-mentioned Gd arrangement method to be integrally molded together with the hydrogen absorbing means, and also examined the rationalization in manufacturing. That is, when the cladding tube is damaged for some reason, the high temperature fuel pellets are oxidized by the infiltrated cooling water, and as a result, hydrogen is generated, and the hydrogen concentration in the cladding tube increases with water vapor.

【0009】これに対して、予め検討された水素吸収性
のすぐれた物質(Zrなど)に加えて、Gdもしくはガ
ドリニア(Gd酸化物)を混合し、それら混合物を水素
透過性のよい被膜で被覆した物質を準備しておく。上記
燃料被覆管において、上記燃料ペレットの近傍部に、上
記の混合物を配設しておけば、発生した水素は、吸収さ
れてしまうので、水素による脆化等の影響は解消され
る。
On the other hand, Gd or gadolinia (Gd oxide) is mixed with a substance (Zr, etc.) having an excellent hydrogen absorbing property which has been studied in advance, and the mixture is covered with a film having good hydrogen permeability. Prepare the substance you prepared. By disposing the mixture in the vicinity of the fuel pellets in the fuel cladding tube, the generated hydrogen is absorbed, and the influence of hydrogen, such as embrittlement, is eliminated.

【0010】一方、この方法によれば、燃焼の初期に
は、燃料ペレットには、割れが少なく、ペレット端面部
には大きな熱膨張変形を生じる傾向があるが、Gdの混
合の影響により、端面部の熱出力が抑制されるようにな
る。燃焼が進行すると、可燃性毒物(Gdなど)の効果
は消失するが、その時の燃料ペレットには多くの亀裂が
発生し、熱膨張による変形は小さくなり、熱出力を抑制
する必要がなくなっている。
On the other hand, according to this method, in the initial stage of combustion, the fuel pellets tend to have few cracks and a large thermal expansion deformation tends to occur at the pellet end face portion. The heat output of the part is suppressed. As combustion progresses, the effect of combustible poisons (Gd, etc.) disappears, but many cracks occur in the fuel pellets at that time, deformation due to thermal expansion becomes small, and there is no need to suppress heat output. .

【0011】[0011]

【実施例】以下本発明の実施例を図1、図2および図3
を用いて説明する。図1は、本発明の核燃料要素の部分
縦断面図である。図1において、1は、核燃料ペレッ
ト、2は、本発明の混合物、3は、水素透過性の被膜、
4は、燃料被覆管である。
Embodiments of the present invention will be described below with reference to FIGS. 1, 2 and 3.
Will be explained. FIG. 1 is a partial vertical sectional view of a nuclear fuel element of the present invention. In FIG. 1, 1 is a nuclear fuel pellet, 2 is a mixture of the present invention, 3 is a hydrogen permeable coating,
4 is a fuel cladding tube.

【0012】すなわち、図1の構成は、核燃料ペレット
1の中間の少なくとも1部に、可燃性毒物(Gdもしく
はその化合物)と水素吸収性のよい物質(ジルコニウム
もしくはその化合物)の混合物2を、水素透過性にすぐ
れた被膜(パラジウム、ランタンもしくはセリウムを主
成分とする物質)3で被覆して1体化成型したものを被
覆管4内に配設したものである。
That is, in the configuration of FIG. 1, a mixture 2 of a burnable poison (Gd or a compound thereof) and a substance having a good hydrogen absorbing property (zirconium or a compound) is charged with hydrogen in at least a part of the middle of the nuclear fuel pellet 1. It is provided in the coating tube 4 by being coated with a coating having excellent permeability (a substance containing palladium, lanthanum or cerium as a main component) 3 and integrally molded.

【0013】本発明によって、原子炉出力上昇時に、燃
料ペレット端面部の熱膨張を抑制する効果がある。ま
た、燃料被覆管の破損時にも水素脆化を防止する効果が
ある。
The present invention has the effect of suppressing the thermal expansion of the end surface of the fuel pellet when the reactor power is increased. Further, it is effective in preventing hydrogen embrittlement even when the fuel cladding tube is damaged.

【0014】図2は、1体化成型した混合物の断面模式
図である。図2は、水素吸収性金属(Zrもしくはその
化合物)をベ−スとしてこれに可燃性毒物(Gdもしく
はその化合物)を混合したものである。図3は、水素吸
収性金属と可燃性毒物の微粒子を均等に混合したもので
ある。いずれの場合も、図1に示した実施例と同等の効
果を示すことはいうまでもない。
FIG. 2 is a schematic cross-sectional view of the single-piece molded mixture. In FIG. 2, a hydrogen-absorbing metal (Zr or its compound) is used as a base and a burnable poison (Gd or its compound) is mixed with this. FIG. 3 shows an even mixture of hydrogen absorbing metal and fine particles of a burnable poison. It goes without saying that in any case, the same effect as that of the embodiment shown in FIG. 1 is exhibited.

【0015】なお、混合物を被覆する被膜については、
水素透過性にすぐれたものであればよい。例えば、パラ
ジウム、ランタン、セリウムを主成分とする物質は水素
透過性物質として検証されている。
Regarding the coating for coating the mixture,
Any material having excellent hydrogen permeability may be used. For example, substances containing palladium, lanthanum and cerium as main components have been verified as hydrogen permeable substances.

【0016】[0016]

【発明の効果】本発明によれば、原子炉出力上昇時に被
覆管内の燃料ペレット端面部の熱膨張を抑制し、被覆管
の局所的な応力集中を緩和することができる。さらに、
核燃料要素が破損することがあっても被覆管の水素脆化
を防止できるので、核燃料要素に対する信頼性を向上さ
せることができる。
According to the present invention, it is possible to suppress the thermal expansion of the end surface portion of the fuel pellet in the cladding tube when the power output of the reactor is increased, and to relieve the local stress concentration in the cladding tube. further,
Even if the nuclear fuel element is damaged, hydrogen embrittlement of the cladding tube can be prevented, so that the reliability of the nuclear fuel element can be improved.

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

【図1】本発明の核燃料要素の部分縦断面図である。FIG. 1 is a partial longitudinal sectional view of a nuclear fuel element of the present invention.

【図2】水素吸収性金属に可燃性毒物粒子を混合した物
質の模式図である。
FIG. 2 is a schematic diagram of a substance in which burnable poison particles are mixed with a hydrogen absorbing metal.

【図3】水素吸収性金属と可燃性毒物粒子を均等に混合
した物質の模式図である。
FIG. 3 is a schematic diagram of a substance in which a hydrogen-absorbing metal and burnable poison particles are uniformly mixed.

【符号の説明】[Explanation of symbols]

1 核燃料ペレット 2 水素吸収性金属と可燃性毒物粒子の混合物 3 水素透過性の被膜 4 被覆管 5 混合物A 6 混合物B 1 Nuclear Fuel Pellet 2 Mixture of Hydrogen Absorbing Metal and Burnable Poison Particles 3 Hydrogen Permeable Coating 4 Cladding Tube 5 Mixture A 6 Mixture B

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 ジルコニウム合金からなる燃料被覆管の
内部に複数個の核燃料ペレットを積層して収納し、上下
の両端栓を密封してなる核燃料要素において、可燃性毒
物と水素吸収性のよい物質を、水素透過性のよい被膜で
被覆して一体化し、前記核燃料ペレット間に配設したこ
とを特徴とする核燃料要素。
1. A nuclear fuel element in which a plurality of nuclear fuel pellets are stacked and housed inside a fuel cladding tube made of a zirconium alloy, and upper and lower end plugs are hermetically sealed, a combustible poison and a substance having a good hydrogen absorbing property. A nuclear fuel element, characterized in that it is covered with a film having good hydrogen permeability and integrated, and is disposed between the nuclear fuel pellets.
【請求項2】 請求項1記載の核燃料要素において、前
記可燃性毒物の主成分は、ガドリニウムもしくはその化
合物、前記水素吸収材の主成分は、ジルコニウムもしく
はその化合物、それらの被覆材は、パラジウム、ランタ
ンもしくはセリウムを主成分とすることを特徴とする核
燃料要素。
2. The nuclear fuel element according to claim 1, wherein the main component of the burnable poison is gadolinium or its compound, the main component of the hydrogen absorbing material is zirconium or its compound, and the coating material thereof is palladium, A nuclear fuel element characterized by mainly containing lanthanum or cerium.
JP2405135A 1990-12-21 1990-12-21 Nuclear fuel element Pending JPH0540186A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2405135A JPH0540186A (en) 1990-12-21 1990-12-21 Nuclear fuel element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2405135A JPH0540186A (en) 1990-12-21 1990-12-21 Nuclear fuel element

Publications (1)

Publication Number Publication Date
JPH0540186A true JPH0540186A (en) 1993-02-19

Family

ID=18514771

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2405135A Pending JPH0540186A (en) 1990-12-21 1990-12-21 Nuclear fuel element

Country Status (1)

Country Link
JP (1) JPH0540186A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0621605A1 (en) * 1993-04-23 1994-10-26 Studsvik Nuclear Ab Nuclear fuel rod with failure alleviating means
JP2014232099A (en) * 2013-05-01 2014-12-11 竹田 眞司 High safety nuclear power generation, high safety fast breeder reactor, radioactive waste treatment, and radioactive contaminated substance removal method
US20180330832A1 (en) * 2017-05-09 2018-11-15 Westinghouse Electric Company Llc Annular nuclear fuel pellets with discrete burnable absorber pins
US11133115B2 (en) * 2019-10-29 2021-09-28 Korea Advanced Institute Of Science And Technology Nuclear fuel rod including disk-type burnable absorber

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0621605A1 (en) * 1993-04-23 1994-10-26 Studsvik Nuclear Ab Nuclear fuel rod with failure alleviating means
JP2014232099A (en) * 2013-05-01 2014-12-11 竹田 眞司 High safety nuclear power generation, high safety fast breeder reactor, radioactive waste treatment, and radioactive contaminated substance removal method
US20180330832A1 (en) * 2017-05-09 2018-11-15 Westinghouse Electric Company Llc Annular nuclear fuel pellets with discrete burnable absorber pins
US11367537B2 (en) * 2017-05-09 2022-06-21 Westinghouse Electric Company Llc Annular nuclear fuel pellets with central burnable absorber
US11133115B2 (en) * 2019-10-29 2021-09-28 Korea Advanced Institute Of Science And Technology Nuclear fuel rod including disk-type burnable absorber

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