JPS58184576A - Nuclear fuel element - Google Patents
Nuclear fuel elementInfo
- Publication number
- JPS58184576A JPS58184576A JP57065522A JP6552282A JPS58184576A JP S58184576 A JPS58184576 A JP S58184576A JP 57065522 A JP57065522 A JP 57065522A JP 6552282 A JP6552282 A JP 6552282A JP S58184576 A JPS58184576 A JP S58184576A
- Authority
- JP
- Japan
- Prior art keywords
- cladding tube
- locking member
- nuclear fuel
- fuel element
- spring
- 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
- Glass Compositions (AREA)
- Catalysts (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】
〔発明の技術分野〕
本発明は、被覆管内に収納された燃料ペレットを弾性的
に押圧するスプリングの一端を形状記憶合金から成る係
止部材で被覆管の内面に固定した核燃料要素に関する。Detailed Description of the Invention [Technical Field of the Invention] The present invention provides a system in which one end of a spring that elastically presses fuel pellets housed in a cladding tube is fixed to the inner surface of a cladding tube with a locking member made of a shape memory alloy. Concerning nuclear fuel elements.
高速増槌形原子力発電所等で使用されている核燃料要素
は、第１図に例示するように、細長い被覆管１内にセラ
ミック系酸化物核燃料ペレット２゜６．４を収納し、被
覆管１の一端近傍にブレナム部５を設け、両端に端栓６
，７を嵌合溶接して密封構造とされている。As illustrated in FIG. 1, the nuclear fuel element used in high-speed multi-ram nuclear power plants, etc. stores ceramic oxide nuclear fuel pellets 2°6.4 in a long and narrow cladding tube 1. A blemish part 5 is provided near one end, and end plugs 6 are provided at both ends.
, 7 are fitted and welded to form a sealed structure.
ここで、端縁部のペレット２．４はＵＯ，ペレットが主
体でブランケット燃料部を形成し、また中央部のペレッ
ト６はＰｕ０ｌ−ＵＯＩ ペレットが主体で炉心燃料
部を形成する。Here, the pellets 2.4 at the edge portion are mainly UO pellets and form a blanket fuel portion, and the pellets 6 at the center portion are mainly Pu0l-UOI pellets and form a core fuel portion.
また、プレナム部５はペレットが核分裂反応に伴なって
発生する核分裂生成ガスを収納して、その寿命中におけ
る被覆管１の内圧があまり上昇しないように設けられた
適当な容積を有する空間である。Further, the plenum part 5 is a space having an appropriate volume and is designed to store the fission product gas generated by the nuclear fission reaction of the pellet and to prevent the internal pressure of the cladding tube 1 from increasing too much during its life. .
このプレナム部５には、燃料ペレブ）２，３゜４が被覆
管１内で移動しないよう、環体９，１０で保持されたス
リーブ８及びスプリング１１が内蔵されている。This plenum portion 5 houses a sleeve 8 and a spring 11 held by rings 9 and 10 so that the fuel pellets 2, 3 and 4 do not move within the cladding tube 1.
このような構造の核燃料要素においては、ペレブ）２，
５．４を保持するためにプレナム部５に挿着される部材
が多くなり、その分だけプレナム部の実効容積が少なく
なる。In nuclear fuel elements with such a structure, Pereb) 2,
5.4, the number of members inserted into the plenum section 5 increases, and the effective volume of the plenum section decreases accordingly.
しかも核燃料要素が長くなり、取扱いが不便であるばか
りでなく、核燃料要素が長くなると原子炉も大きくなり
、経済的にも不利益を招くという欠点がある。Moreover, the nuclear fuel element becomes longer, which is not only inconvenient to handle, but also the longer the nuclear fuel element becomes, the larger the reactor becomes, resulting in an economical disadvantage.
また、第２図に例示するように、スプリング１１の一端
を圧縮体１２で被覆管１の内面に係止する１・：′１
方法も知られているが、圧縮体１２の取付に際して、特
別な治具を用いて複雑な工程を経なければならない。Furthermore, as illustrated in FIG. 2, a method is also known in which one end of the spring 11 is locked to the inner surface of the cladding tube 1 with a compression body 12, but when installing the compression body 12, special It requires a complicated process using special jigs.
また圧縮体１２を被覆管１内に所定の精度で係止できな
いことがあり、この場合には、圧縮体１２を一旦燃料要
素内より除去し、再装着することが必要であり、多大の
困難を伴う。Furthermore, the compression body 12 may not be locked within the cladding tube 1 with a predetermined precision, and in this case, it is necessary to temporarily remove the compression body 12 from within the fuel element and reinstall it, which causes great difficulty. accompanied by.
また、組立ての自動化や組立費用などの点でも問題があ
る。There are also problems in terms of assembly automation and assembly costs.
本発明は背景技術における上述の如き不都合を除去すべ
くなされたもので、プレナム部の実効容積を減らすこと
なく、燃料ペレットを有効に保持し、しかも組立ての簡
単な核燃料要素を提供しようとするものである。The present invention has been made in order to eliminate the above-mentioned disadvantages in the background art, and aims to provide a nuclear fuel element that can effectively hold fuel pellets without reducing the effective volume of the plenum and is easy to assemble. It is.
本発明の核燃料要素は、被覆管と、これに収納した燃料
ペレットと、前記被覆管の両端をシールする端栓と、前
記燃料を弾性的に押圧するスプリングと、このスプリン
グの他端側な被覆管の内面・、ｉ
に係止する形状記憶合金製の係止部材とから構成されて
いる。The nuclear fuel element of the present invention includes a cladding tube, fuel pellets stored in the cladding tube, end plugs that seal both ends of the cladding tube, a spring that elastically presses the fuel, and a cladding on the other end of the spring. It consists of a locking member made of a shape memory alloy that locks onto the inner surface of the tube.
以下、第３図ないし第６図を参照して本発明の詳細な説
明する。Hereinafter, the present invention will be described in detail with reference to FIGS. 3 to 6.
なお、これらの図において、第１図および第２図におけ
ると同一の部材にはそれと同じ番号を付しである。In these figures, the same members as in FIGS. 1 and 2 are given the same numbers.
第６図において、ステンレス鋼等から成る被覆管１には
炉心燃料部およびブランケット燃料部を形成する複数個
の燃料ペレット４が収納され、被覆管１の両端は端栓７
により気密にシールされている。In FIG. 6, a plurality of fuel pellets 4 forming a core fuel section and a blanket fuel section are housed in a cladding tube 1 made of stainless steel or the like, and both ends of the cladding tube 1 are provided with end plugs 7.
is hermetically sealed.
ペレット４と端栓７の間に形成されたプレナム部５には
スプリング１１が収納され、その一端はペレット４の端
面に接触している。A spring 11 is housed in a plenum 5 formed between the pellet 4 and the end plug 7, and one end of the spring 11 is in contact with the end surface of the pellet 4.
スプリング１１の他端側はスプリング押え部材１６を介
して、形状記憶合金から成る係止部材１４に圧接してい
る。The other end of the spring 11 is in pressure contact with a locking member 14 made of a shape memory alloy via a spring pressing member 16.
形状記憶合金は、特定の温度あるいは応力の下で、マル
テンサイトとして知られている原子配列に変態および逆
変態できる結晶構造を有するもので、銅・亜鉛・アルミ
ニウム合金、ニッケル・チタン合金、鉄・ニッケル合金
、ニッケル・アルミニウム合金、鉄・白金合金などがあ
る。Shape memory alloys have a crystalline structure that can transform and reverse into an atomic arrangement known as martensite under specific temperatures or stress, and include copper-zinc-aluminum alloys, nickel-titanium alloys, iron-titanium alloys, There are nickel alloys, nickel-aluminum alloys, iron-platinum alloys, etc.
本発明の係止部材にはニッケル・チタン合金が適してい
るが他の合金系でもよい。A nickel-titanium alloy is suitable for the locking member of the present invention, but other alloys may also be used.
この形状記憶合金、例えばニッケル・チタン合金は０．
６謳程度に線引きされ、第４図（１）に示すように、被
覆管１の内径よりやや大径の外径を有する数輪のコイル
状の係止部材１４に加工される。This shape memory alloy, such as a nickel-titanium alloy, has a 0.
The wire is drawn into about 6 pieces, and as shown in FIG. 4(1), it is processed into a several-ring coil-shaped locking member 14 having an outer diameter slightly larger than the inner diameter of the cladding tube 1.
この加工はニッケル・チタン合金の母相の状態で行なわ
れる。This processing is performed in the state of the nickel-titanium alloy matrix.
次に、核燃料要素が加工された後、原子炉に装荷される
までの間の通常の周囲温度以下の所定の温度まで係止部
材１４を冷却し、第４図（ａ）がら申）に示すように係
止部材１４の両端を伸長するが、あるいはコイルの一端
部を固定し、他端に回転力を加えることによりその外径
を被覆管内径より小径にする。Next, after the nuclear fuel element is processed, the locking member 14 is cooled to a predetermined temperature below the normal ambient temperature before being loaded into the reactor, as shown in FIG. 4(a). Either ends of the locking member 14 are extended, or one end of the coil is fixed and a rotational force is applied to the other end to make its outer diameter smaller than the inner diameter of the cladding tube.
こ、の冷却温度は、ドライアイス、液体窒素あるいは液
体ヘリウム等によって容易に得られる。This cooling temperature can be easily obtained using dry ice, liquid nitrogen, liquid helium, or the like.
このようにして縮径された係止部材は、未だ冷えている
うちに、核燃料要素のブレナム部５内の所定位置に、装
置される。The locking member whose diameter has been reduced in this manner is placed in a predetermined position within the blemish part 5 of the nuclear fuel element while it is still cold.
係止部材１４は、プレナム部５内に挿着後、その温度が
室温程度化に戻る間に変態点を通過する際、第４図（１
）のように元の外径に復帰して被覆管１の内面に圧接す
る。After the locking member 14 is inserted into the plenum portion 5, the locking member 14 passes through a transformation point while the temperature returns to room temperature, as shown in FIG. 4 (1).
), it returns to its original outer diameter and comes into pressure contact with the inner surface of the cladding tube 1.
従ってスプリング１１の一端はスプリング押え部材１６
と、係止部材１４を介して被覆管１内の所定位装置に固
定される。Therefore, one end of the spring 11 is connected to the spring pressing member 16.
Then, it is fixed to a predetermined position device within the cladding tube 1 via the locking member 14.
係止部材１４は元の形状に復帰した状態では、被覆管内
面に圧接するよう、そのコイル外径を選定されているの
で、スプリング１１が移動するようなことは無い。Since the outer diameter of the coil is selected so that the locking member 14 is in pressure contact with the inner surface of the cladding tube when it has returned to its original shape, the spring 11 will not move.
また燃料要素の組立の際には、単に係止部材１４を急冷
し、その外径を被覆管内径より小径にして、被覆管内に
挿入するだけで良く、挿着および組立操作は非常に簡単
である。Furthermore, when assembling the fuel element, it is sufficient to simply rapidly cool the locking member 14, make its outer diameter smaller than the inner diameter of the cladding tube, and insert it into the cladding tube, making the insertion and assembly operations very easy. be.
あい３ユ、−０゜、５イ、−一、□６゜形量は、温度差
が約１００℃あっても０．２％程度（ステンレス鋼）で
あるが、本発明の場合には、完全に回復可能な変形量は
６〜８％程度に達するので、操着作業は容易であり・、
また、係止力も大きい。The shape amount of A3U, -0°, 5i, -1, □6° is about 0.2% (stainless steel) even if the temperature difference is about 100°C, but in the case of the present invention, The amount of deformation that can be completely recovered is about 6-8%, so the operation is easy.
Also, the locking force is large.
また組立操作上の不具合いがあった場合には被覆管１の
外周囲より係止部材１４を冷却することにより、その外
径を小径にして容易に被覆管内から除去し、再度被覆管
内の所定位置に装着することができる。In addition, if there is a problem with the assembly operation, by cooling the locking member 14 from the outer periphery of the cladding tube 1, the outer diameter of the locking member 14 can be reduced to a smaller diameter, so that it can be easily removed from the cladding tube, and the locking member 14 can be easily removed from the inside of the cladding tube. Can be mounted in any position.
また、係止部材１４は、線径０．６ｍ程度の細線をコイ
ル状に巻回した線輪で構成することができ、その実効体
積は非常に少ない。Further, the locking member 14 can be formed of a wire ring made by winding a thin wire with a wire diameter of about 0.6 m into a coil shape, and its effective volume is very small.
従ってプレナム部５の実効容積を減らすことが少ないた
め、核燃料要素の長さを長くする必要がなく、プレナム
部容積の大きな核燃料要素を提供することができる。Therefore, since the effective volume of the plenum portion 5 is not reduced much, there is no need to increase the length of the nuclear fuel element, and a nuclear fuel element with a large plenum volume can be provided.
なお、本発明は第５図および第６図のように変形して適
用することも可能である。Note that the present invention can also be applied in a modified manner as shown in FIGS. 5 and 6.
この実施例では、係止部材１５としてスリット１６を有
する円筒体が使用されている。In this embodiment, a cylindrical body having a slit 16 is used as the locking member 15.
この係止部材はニッケル・チタン合金等の形状記憶合金
な母相の状態で加工し、被覆管１の内径よりやや大きな
外径を有し、長手方向にスリットが加工された円筒体と
したもので、その後急冷し、ｓ６図（ｂ） Ｉｍ示す様
に係止部材１５の外周囲を押圧して外径を被覆管１の内
径より小径にして被覆管１内に挿着される。This locking member is made into a cylindrical body made of a shape memory alloy matrix such as a nickel-titanium alloy, and has an outer diameter slightly larger than the inner diameter of the cladding tube 1, and has a slit machined in the longitudinal direction. Then, it is rapidly cooled, and the outer periphery of the locking member 15 is pressed to make the outer diameter smaller than the inner diameter of the cladding tube 1, and the locking member 15 is inserted into the cladding tube 1, as shown in FIG.
この係止部材１５も、挿着後、温度が室温程度に戻る間
に変態点を通過する際、第６図（ａ）のように元の外径
に復帰して被覆管１の内面に圧接する。After insertion, when the locking member 15 passes through a transformation point while the temperature returns to around room temperature, it returns to its original outer diameter as shown in FIG. 6(a) and comes into pressure contact with the inner surface of the cladding tube 1. do.
従って、スプリング１１の一端は係止部材１５を介して
被覆管１内の所定位置に固定される。Therefore, one end of the spring 11 is fixed at a predetermined position within the cladding tube 1 via the locking member 15.
以上説明したように、本発明の核燃料要素においては、
形状記憶合金で形成された係止部材によってスプリング
を係止するようにしたから、組み立ては係止部材を冷却
し、その外径を小径にした後、被覆管内に挿着するだけ
で簡単に行なうことができ、また挿着に不具合が生じた
場合でも、係止部材を冷却することによりこれを簡単に
除去することができ、しかも、プレナム部の実効容積の
大きい核燃料要素を得ることができる。As explained above, in the nuclear fuel element of the present invention,
Since the spring is locked with a locking member made of shape memory alloy, assembly is as simple as cooling the locking member, reducing its outer diameter to a small diameter, and then inserting it into the cladding tube. Furthermore, even if a problem occurs during insertion, it can be easily removed by cooling the locking member, and a nuclear fuel element with a large effective volume of the plenum portion can be obtained.
第１図および第２図は夫々、従来の核燃料要素を例示す
る縦断面図、第６図は本発明の核燃料要素の実施例の主
要部分を示す縦断面図、第４図（ａ）。
（ｂ）は第６図における係止部材１４の変形前後の状態
を示す縦断面図、第５図は本発明の核燃料要素の変形例
の主要部分を示す縦断面図、第６図（ａ）。
（ｂ）は第５図における係止部材１５の変形前後の状態
を示す縦断面図である。
１ ・・・・・・・・・・・・・・・被覆管２．５．４
・・・ 燃料ベレット
５ ・・・・・・・・・・・・・・・ プレナム部６．
７ ・・・・・・・・・ 端栓
８ ・・・・・・・・・・・・・・・ スリーブ９．１
０ ・・・・・・・・・ 環体
１１ ・・・・・・・・・・・・・・・ スプリング
１２ ・・・・・・・・・・・・・・・ 圧縮体１６
・・・・・・・・・・・・・・・ スプリング押え部材
１４．１５ ・・・・・・・・・ 係止部材１６ ・
・・・・・・・・・・・・・・ スリット第１図
第２図
＋／ ／２互
第３図
第５図
ｖＩＳＧ図1 and 2 are longitudinal sectional views illustrating a conventional nuclear fuel element, FIG. 6 is a longitudinal sectional view showing main parts of an embodiment of the nuclear fuel element of the present invention, and FIG. 4(a). (b) is a vertical sectional view showing the states of the locking member 14 before and after deformation in FIG. 6, FIG. 5 is a vertical sectional view showing the main parts of a modified example of the nuclear fuel element of the present invention, and FIG. 6(a) . (b) is a longitudinal cross-sectional view showing the state of the locking member 15 in FIG. 5 before and after deformation. 1 ・・・・・・・・・・・・・・・Claying tube 2.5.4
・・・ Fuel pellet 5 ・・・・・・・・・・・・・・・ Plenum part 6.
7 ・・・・・・・・・ End plug 8 ・・・・・・・・・・・・・・・ Sleeve 9.1
0 ・・・・・・・・・ Ring body 11 ・・・・・・・・・・・・ Spring 12 ・・・・・・・・・・・・ Compression body 16
...... Spring holding member 14.15 ...... Locking member 16 ・
・・・・・・・・・・・・・・・ Slit Figure 1 Figure 2 +/ /2 Alternate Figure 3 Figure 5 vISG diagram
Claims (1)
覆管の両端をシールする端栓と、前記燃料を弾性的に押
圧するスプリングと、このスプリングの他端側を被覆管
の内面に係止する形状記憶合金製の係止部材とから成る
ことを特徴とする核燃料要素。 ２、係止部材が、形状記憶合金製の細線な母相状態にお
いて、被覆管の内径よりもやや大径のコイル状に加工し
、これを冷却状態で縮径させて前記被覆管内に挿着した
後、復元させたものであることを特徴とする特許請求の
範囲第１項に記載の核燃料要素。 ６、係止部材が長さ方向に沿ってスリットを有する円筒
体から成り、冷却状態で縮径させて被覆管内に挿着した
後、復元させたものであることを特徴とする特許請求の
範ｖ！Ａ第１項に記載の核燃料要素。[Claims] 1. A cladding tube, fuel pellets stored in the cladding tube, end plugs that seal both ends of the cladding tube, a spring that elastically presses the fuel, and a spring that presses the other end of the spring. A nuclear fuel element comprising a locking member made of a shape memory alloy that locks onto the inner surface of a cladding tube. 2. The locking member is a thin wire matrix made of a shape memory alloy, which is processed into a coil shape with a diameter slightly larger than the inner diameter of the cladding tube, and the diameter of this is reduced in a cooled state and inserted into the cladding tube. The nuclear fuel element according to claim 1, wherein the nuclear fuel element is restored after being 6. Claims characterized in that the locking member is made of a cylindrical body having a slit along its length, and is restored after being reduced in diameter in a cooled state and inserted into a cladding tube. v! A nuclear fuel element according to paragraph 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57065522A JPS58184576A (en) | 1982-04-21 | 1982-04-21 | Nuclear fuel element |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57065522A JPS58184576A (en) | 1982-04-21 | 1982-04-21 | Nuclear fuel element |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS58184576A true JPS58184576A (en) | 1983-10-28 |
Family
ID=13289434
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57065522A Pending JPS58184576A (en) | 1982-04-21 | 1982-04-21 | Nuclear fuel element |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58184576A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6117693U (en) * | 1984-07-05 | 1986-02-01 | 株式会社東芝 | nuclear fuel rod |
| JPH02231595A (en) * | 1989-03-03 | 1990-09-13 | Power Reactor & Nuclear Fuel Dev Corp | Fuel cladding pipe for fast breeder reactor and production thereof |
| JPH0679386U (en) * | 1993-04-23 | 1994-11-08 | 株式会社サンアイ | Soap bag |
-
1982
- 1982-04-21 JP JP57065522A patent/JPS58184576A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6117693U (en) * | 1984-07-05 | 1986-02-01 | 株式会社東芝 | nuclear fuel rod |
| JPS64636Y2 (en) * | 1984-07-05 | 1989-01-09 | ||
| JPH02231595A (en) * | 1989-03-03 | 1990-09-13 | Power Reactor & Nuclear Fuel Dev Corp | Fuel cladding pipe for fast breeder reactor and production thereof |
| JPH0679386U (en) * | 1993-04-23 | 1994-11-08 | 株式会社サンアイ | Soap bag |
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