JPS5940195A - Nuclear fuel element for fast breeder - Google Patents
Nuclear fuel element for fast breederInfo
- Publication number
- JPS5940195A JPS5940195A JP57149952A JP14995282A JPS5940195A JP S5940195 A JPS5940195 A JP S5940195A JP 57149952 A JP57149952 A JP 57149952A JP 14995282 A JP14995282 A JP 14995282A JP S5940195 A JPS5940195 A JP S5940195A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel element
- cladding tube
- fast breeder
- cladding
- 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
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】
〔発明の技術分野〕
本発明は高速増殖炉用核燃料要素に関し、更に詳しくは
、被覆管強度の低下を防止し得る高速増殖炉用核燃料要
素に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a nuclear fuel element for a fast breeder reactor, and more particularly to a nuclear fuel element for a fast breeder reactor that can prevent a decrease in cladding strength.
現在、原子力発電において、高速増殖炉は、大エネルギ
ー量ヲウラン資源から取出し得ることから、軽水炉に代
わる原子炉としてその研究が進められている。Currently, in nuclear power generation, fast breeder reactors are being researched as a nuclear reactor to replace light water reactors because they can extract a large amount of energy from uranium resources.
近年、高速増殖炉用燃料要素の核燃料としては、溶融点
が高く、かつ冷却材のナトリウムに対する安定性が高く
、シかも高焼結度にも嗣えるなどの理由から、酸化ウラ
／と酸化プルトニウムとの混合物が多用されるようにな
った。In recent years, ura/plutonium oxide has been used as nuclear fuel for fast breeder reactor fuel elements because of its high melting point, high stability against sodium coolant, and ability to withstand high degrees of sintering. Mixtures with are now widely used.
この核燃料は、細長い被覆管の中に充填されて核燃料要
素を構成する。被覆管の拐質としては、通常Ｆｅ −Ｎ
ｉ −Ｃｒ合金（例えば、ステンレス鋼）が採用されて
いる。This nuclear fuel is filled into an elongated cladding tube to constitute a nuclear fuel element. The material for the cladding tube is usually Fe-N.
An i-Cr alloy (eg, stainless steel) is employed.
このような核燃料要素について、高速増殖炉内での使用
後に強度試験を行なった際、その被覆管の強度が異常に
低下していることが報告されている。デー・アール・ダ
ンヵンラ、トランスアクションズ・オブ・ザ°アメリカ
ン・ンザエティ、第３８巻、２６５頁、１９８１年ＣＤ
、 Ｒ，Ｄｕｎｃａｎ ｅｔ ａｌ、 。It has been reported that when such a nuclear fuel element is subjected to a strength test after being used in a fast breeder reactor, the strength of its cladding tube is abnormally reduced. D. R. Duncanra, Transactions of the American Society, Volume 38, Page 265, 1981 CD
, R. Duncan et al.
Ｔｒａｎｓａｃｔｉｏｎｓ ｏｆ ｔｈｅ Ａｍｅｒｉ
ｃａｎ ５ｏｃｉｅｔｙ ｌ ３８ ｐ２６５ （１９
８１））、エム・ジー・アダムソンら、同上、第３９頁
、３８５頁、１９８１年ＣＭ、 Ｇ。Transactions of the Ameri
can 5ociety l 38 p265 (19
81)), M.G. Adamson et al., supra, pp. 39, 385, 1981 CM, G.
Ａｄａｍｓｏｎ ｅｔ ａｌ、ｙ １ｂｌｄ ｐ
３９ ｅ ３８５（１９８１））等参照。Adamson et al, y 1bld p.
39 e 385 (1981)) etc.
この被覆管の強度低下は、核燃料要素の寿命を短縮し、
また炉の運転時における破損等の危険性を増大させる原
因ともなるため、核燃料要素としての信頼性を低下させ
る。This reduction in cladding strength shortens the lifetime of the nuclear fuel element and
It also increases the risk of damage during reactor operation, reducing its reliability as a nuclear fuel element.
上記した被覆管の強度低下現象は燃料隣接効果と呼ばれ
ている。この効果は、被覆管内表面に付着した酸化ウラ
ン及び酸化プルトニウムの核***生成物であるＣ８及び
Ｔｅが原因であると考えられている。更に、核燃料物質
との接触又はガス状核***生成物の内圧力等によシ、被
覆管に加わる応力がある閾値を超えると、燃料隣接効果
の発生することが考えられる。また、この効果は、Ｃ！
ＩとＴｅとが一定の混合比、即ち１：１にあるときに生
じることが判明している。The above-mentioned phenomenon in which the strength of the cladding tube decreases is called the fuel adjacency effect. This effect is thought to be caused by C8 and Te, which are fission products of uranium oxide and plutonium oxide, which adhere to the inner surface of the cladding tube. Further, if the stress applied to the cladding exceeds a certain threshold due to contact with nuclear fuel material or internal pressure of gaseous fission products, fuel adjacency effects may occur. Also, this effect is C!
It has been found that this occurs when I and Te are in a certain mixing ratio, ie 1:1.
従って、被覆管強度低下を防止するためには、ＣｓとＴ
ｅとが所定の混合比で生成しないよ−うに核燃料の酸化
ウランと酸化プルトニウムの混合比を変えることが考え
られるが、こうした場合、発生するエネルギー量の低下
が避けられない。Therefore, in order to prevent the cladding strength from decreasing, Cs and T
It is conceivable to change the mixture ratio of uranium oxide and plutonium oxide in the nuclear fuel so that uranium oxide and plutonium oxide are not generated at a predetermined mixture ratio, but in such a case, a decrease in the amount of energy generated is unavoidable.
そこで、上記以外の方法によって燃料隣接効果を防止し
、もって核燃料要素の信頼性向上及び長寿命化を図るこ
とが望まれる。Therefore, it is desired to prevent the fuel adjacency effect by methods other than those described above, thereby improving the reliability and extending the life of nuclear fuel elements.
本発明の目的は、信頼性が向上し、かつ長寿命である高
速増殖炉用核燃料要素を提供するととにある。An object of the present invention is to provide a nuclear fuel element for a fast breeder reactor with improved reliability and long life.
即ち、本発明は被覆管内に酸化ウラン及び酸化プルトニ
ウムを含有した核燃料物質を充填して成る高速増殖炉用
核燃料要素において、前記被覆管の内面にζ被覆管の材
質よシもＴｅ又はＣｅと金属間化合物を生成し易い拐質
から成る金属保護層を一体的に形成したことを特徴とす
る。That is, the present invention provides a nuclear fuel element for a fast breeder reactor in which a nuclear fuel material containing uranium oxide and plutonium oxide is filled in a cladding tube, in which the inner surface of the cladding tube is coated with Te or Ce and metals other than the material of the ζ cladding tube. It is characterized by integrally forming a metal protective layer made of particulate matter that is likely to generate intercalary compounds.
以下に本発明の核燃料要素を第１図及び第２図に示した
１実施例に基づき詳細に説明する。第１図は本発明核燃
料要素の縦断面図、第２図は第１図のＡ−Ａ線に沿う縦
断面図である。The nuclear fuel element of the present invention will be explained in detail below based on one embodiment shown in FIGS. 1 and 2. FIG. 1 is a longitudinal sectional view of the nuclear fuel element of the present invention, and FIG. 2 is a longitudinal sectional view taken along line A--A in FIG.
図中、１は被覆管である。該被覆管１は通常円筒型で、
その材質は通常ステンレス鋼から成る。In the figure, 1 is a cladding tube. The cladding tube 1 is usually cylindrical,
Its material usually consists of stainless steel.
ステンレス鋼の具体例としては、ＳＵＳ ３１６があげ
られる。A specific example of stainless steel is SUS 316.
２及び３は夫々上部端栓、下部端栓であって、被・直管
ｌに冠着される。その材質は通常被覆管１と同月質であ
る。Reference numerals 2 and 3 denote an upper end plug and a lower end plug, respectively, which are attached to the straight pipe l. Its material is usually the same as that of the cladding tube 1.
４はスプリング、５はスリーブ、６は燃料ペレットであ
って、夫々被覆管１内に装填されている。4 is a spring, 5 is a sleeve, and 6 is a fuel pellet, each of which is loaded into the cladding tube 1.
燃料ペレット６には、通常所定比に混合された酸化ウラ
ン及び酸化プルトニウムを焼結法あるいは振動充填法に
より充分に均一化をはかｐ高密化してベレットとしたも
のが使用される。The fuel pellets 6 are usually pellets obtained by sufficiently homogenizing uranium oxide and plutonium oxide mixed in a predetermined ratio by a sintering method or a vibration filling method, and then densifying the pellets.
７は被覆管１の内面に形成された保護層である。7 is a protective layer formed on the inner surface of the cladding tube 1.
保護層７と被覆管１とは一体化構造になっていて、複合
被恒管８を構成している。保護層７の材質は、被覆管１
の材質よシもＴｏ又はＣＢと金属間化合物を生成し易く
、かつ延性に富む金属又は合金から選択される。また延
性の点から高純度であることが好丑しく、更には不純物
としての酸素の濃度が小さいもの程一層効果的である。The protective layer 7 and the cladding tube 1 have an integrated structure and constitute a composite tube 8 to be fixed. The material of the protective layer 7 is the material of the cladding tube 1.
The material is selected from metals or alloys that easily form intermetallic compounds with To or CB and are highly ductile. Further, from the viewpoint of ductility, high purity is preferable, and furthermore, the lower the concentration of oxygen as an impurity, the more effective it is.
被覆管１の材質が例えばＳＵＳ ３１６ステンレス鋼で
ある場合には、保護層７の材質はＣｕ 、 Ｆｅ 。When the material of the cladding tube 1 is, for example, SUS 316 stainless steel, the material of the protective layer 7 is Cu or Fe.
Ｎｉ ｒ Ｔｉ ｒ Ｍｅ ｒ Ｎｂ ＋ Ｚｒ ｅ
Ｃｒから選ばれる１種の金属又は２種以上の合金である
ことが好ましい。Ni r Ti r Me r Nb + Zr e
Preferably, it is one type of metal selected from Cr or an alloy of two or more types.
これらのうち、複合被覆管８の製造容易性及び耐食性の
観点からはＣｕ 、 Ｔｉ ＋ Ｎｉ 、 Ｎｂ 、
Ｚｒが好ましい。このうち熱伝導率及び熱膨張率を考慮
すると、Ｃｕが最も好ましい。Among these, from the viewpoint of ease of manufacture and corrosion resistance of the composite cladding tube 8, Cu, Ti + Ni, Nb,
Zr is preferred. Among these, Cu is most preferable in consideration of thermal conductivity and thermal expansion coefficient.
伺、保護層７は単層であってもよいし、各種の金属又は
合金から成る多重層でβってもよい。However, the protective layer 7 may be a single layer or may be a multilayer consisting of various metals or alloys.
上記した保護層７は、例えば次のようにして被覆管１の
内面に形成される。即ち、加工して所定寸法形状にする
前の被覆管１の中に上記金属もしくは合金のパイプを密
着して嵌挿しておき、両者を所定の厚みになるまで同時
に熱間引き抜きする方法、又は予め所定寸法に加工され
た被覆管の内壁にこれら金属を所定の厚みに析出せしめ
るメッキ法などを適用することができる。The above-mentioned protective layer 7 is formed on the inner surface of the cladding tube 1, for example, in the following manner. That is, the metal or alloy pipe is closely fitted into the cladding tube 1 before it is processed into a predetermined size and shape, and both are hot-drawn at the same time until they reach a predetermined thickness. A plating method or the like can be applied to deposit these metals to a predetermined thickness on the inner wall of a cladding tube that has been processed to predetermined dimensions.
本発明の核燃料要素においては、酸化ウラン及び酸化プ
ルトニウムの核***生成物の一種でおるＣｓ及びＴｅが
、直接に被覆管１と接触することはない。よって、Ｃ６
及びＴｏは保護層７の内面に付着し、次第にＣｓ及びＴ
ｅのいずれか一方あるいは両者が保護層７と反応して金
属間生成物を生成することによシ核燃料要素内のＣｓと
Ｔｏとの混合比が変わる。In the nuclear fuel element of the present invention, Cs and Te, which are types of fission products of uranium oxide and plutonium oxide, do not come into direct contact with the cladding tube 1. Therefore, C6
and To adhere to the inner surface of the protective layer 7, and gradually Cs and T
The mixing ratio of Cs and To in the nuclear fuel element changes when one or both of e reacts with the protective layer 7 to generate an intermetallic product.
また、保護層７は、延性に富むため、燃料ペレット６の
膨張又はガス状核***生成物の内圧力等による被覆管１
への応力を吸収・緩和する機能を有する。In addition, since the protective layer 7 is highly ductile, the cladding tube 1 can be damaged by the expansion of the fuel pellets 6 or the internal pressure of gaseous fission products.
It has the function of absorbing and relieving stress.
以上の理由から、燃料隣接効果は抑制され、被覆管１の
強度低下防止が図られる。For the above reasons, the fuel adjacency effect is suppressed and the strength of the cladding tube 1 is prevented from decreasing.
伺、本発明の核燃料要素では、核***生成物を核燃料要
素から放出するようなベント型燃料要素であってもよい
ことは自明であろう。何故ならばベント型燃料要素にあ
っても、核***生成物は複合被覆管の内面に接触してい
るからである。また、燃料隣接効果は燃料カラム部に位
置する被覆管上のみ観察される現象なので保設層７は少
なくとも燃料カラム部に位置する被覆管に存在すればよ
い。However, it will be obvious that the nuclear fuel element of the present invention may be a vented fuel element that releases fission products from the nuclear fuel element. This is because even in a vented fuel element, fission products are in contact with the inner surface of the composite cladding. Further, since the fuel adjacency effect is a phenomenon observed only on the cladding tube located in the fuel column portion, the storage layer 7 only needs to be present on the cladding tube located in the fuel column portion.
本発明の高速増殖炉用核燃料要素は、保護層によって、
燃料の核***生成物であるＣｓ及びＴｏから被覆管を隔
絶し、かつ被覆管へ加わる応力の吸収・緩和材として機
能するので、両者間の燃料隣接効果が生じない。従って
、被覆管の強度が低下するおそれはなくなり、その強度
は設計基準値を保持し得るため、極めて信頼性が高く、
かつ耐用寿命の長い核燃料要素となるものである。The nuclear fuel element for a fast breeder reactor of the present invention has the following features by the protective layer:
Since it isolates the cladding from Cs and To, which are nuclear fission products of the fuel, and functions as a stress absorbing/relaxing material applied to the cladding, no fuel adjacency effect occurs between the two. Therefore, there is no risk that the strength of the cladding will decrease, and the strength can maintain the design standard value, making it extremely reliable.
It also serves as a nuclear fuel element with a long service life.
第１図は本発明核燃料要素の一部切欠縦断面図、第２図
は第１図のＡ−Ａ線に沿う縦断面図である。
１・・・被覆管、２・・・上部端栓、３・・・下部端栓
、４・・・スプリング、５・・・スリーブ、６・・・燃
料ベレット、７・・・保護層、８・・・複合被覆管。FIG. 1 is a partially cutaway vertical cross-sectional view of a nuclear fuel element of the present invention, and FIG. 2 is a vertical cross-sectional view taken along line A--A in FIG. 1. DESCRIPTION OF SYMBOLS 1... Cladding tube, 2... Upper end plug, 3... Lower end plug, 4... Spring, 5... Sleeve, 6... Fuel pellet, 7... Protective layer, 8 ...Composite cladding.
Claims (1)
核燃料物質を充填して成る高速増殖炉用核燃料要素にお
いて、 前記被覆管の内面に、被覆管の材質よシもＴｅ又はＣｓ
と金属間化合物を生成し易い材質から成る金属保獲層を
一体的に形成したことを特徴とする高速増殖炉用核燃料
要素。[Scope of Claims] A nuclear fuel element for a fast breeder reactor in which a cladding tube is filled with a nuclear fuel material containing uranium oxide and plutonium oxide, wherein the inner surface of the cladding tube is made of Te or Cs.
A nuclear fuel element for a fast breeder reactor, characterized by integrally forming a metal retention layer made of a material that easily generates intermetallic compounds.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57149952A JPS5940195A (en) | 1982-08-31 | 1982-08-31 | Nuclear fuel element for fast breeder |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57149952A JPS5940195A (en) | 1982-08-31 | 1982-08-31 | Nuclear fuel element for fast breeder |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5940195A true JPS5940195A (en) | 1984-03-05 |
Family
ID=15486171
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57149952A Pending JPS5940195A (en) | 1982-08-31 | 1982-08-31 | Nuclear fuel element for fast breeder |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5940195A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7867430B2 (en) | 2009-05-20 | 2011-01-11 | Samsung Electronics Co., Ltd. | Injection mold and injection molding method using the same |
| CN111326265A (en) * | 2020-02-28 | 2020-06-23 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
| US11634810B2 (en) * | 2016-09-28 | 2023-04-25 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Process of manufacture a nuclear component with metal substrate by DLI-MOCVD and method against oxidation/hydriding of nuclear component |
-
1982
- 1982-08-31 JP JP57149952A patent/JPS5940195A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7867430B2 (en) | 2009-05-20 | 2011-01-11 | Samsung Electronics Co., Ltd. | Injection mold and injection molding method using the same |
| US11634810B2 (en) * | 2016-09-28 | 2023-04-25 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Process of manufacture a nuclear component with metal substrate by DLI-MOCVD and method against oxidation/hydriding of nuclear component |
| CN111326265A (en) * | 2020-02-28 | 2020-06-23 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
| CN111326265B (en) * | 2020-02-28 | 2023-05-02 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
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