JPH01113699A - Assembling of nuclear fuel assembly - Google Patents
Assembling of nuclear fuel assemblyInfo
- Publication number
- JPH01113699A JPH01113699A JP62270540A JP27054087A JPH01113699A JP H01113699 A JPH01113699 A JP H01113699A JP 62270540 A JP62270540 A JP 62270540A JP 27054087 A JP27054087 A JP 27054087A JP H01113699 A JPH01113699 A JP H01113699A
- Authority
- JP
- Japan
- Prior art keywords
- spacer
- fuel rod
- thin film
- fuel
- support
- 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.)
- Granted
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 17
- 239000000446 fuel Substances 0.000 claims abstract description 72
- 125000006850 spacer group Chemical group 0.000 claims abstract description 69
- 239000010409 thin film Substances 0.000 claims abstract description 36
- 238000000034 method Methods 0.000 claims abstract description 18
- 229910052751 metal Inorganic materials 0.000 claims abstract description 17
- 239000002184 metal Substances 0.000 claims abstract description 17
- 239000011347 resin Substances 0.000 claims description 17
- 229920005989 resin Polymers 0.000 claims description 17
- 238000003780 insertion Methods 0.000 abstract description 4
- 230000037431 insertion Effects 0.000 abstract description 4
- 230000000149 penetrating effect Effects 0.000 abstract 1
- 230000002093 peripheral effect Effects 0.000 description 10
- 229920006267 polyester film Polymers 0.000 description 6
- 239000000020 Nitrocellulose Substances 0.000 description 3
- 229920001220 nitrocellulos Polymers 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000010408 film Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- SMZOUWXMTYCWNB-UHFFFAOYSA-N 2-(2-methoxy-5-methylphenyl)ethanamine Chemical compound COC1=CC=C(C)C=C1CCN SMZOUWXMTYCWNB-UHFFFAOYSA-N 0.000 description 1
- NIXOWILDQLNWCW-UHFFFAOYSA-N 2-Propenoic acid Natural products OC(=O)C=C NIXOWILDQLNWCW-UHFFFAOYSA-N 0.000 description 1
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 1
- XTXRWKRVRITETP-UHFFFAOYSA-N Vinyl acetate Chemical compound CC(=O)OC=C XTXRWKRVRITETP-UHFFFAOYSA-N 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 229920000728 polyester Polymers 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
「産業上の利用分野」
この発明は、核燃料集合体組立方法に係わり、特に核燃
料集合体を組み立てる際に、燃料棒の外周部へのスクラ
ッヂ発生を防止することができるものに関する。[Detailed Description of the Invention] "Industrial Application Field" The present invention relates to a method for assembling a nuclear fuel assembly, and in particular, it is possible to prevent the generation of scratch on the outer periphery of a fuel rod when assembling a nuclear fuel assembly. related to things.
「従来の技術」
加圧水型軽水炉等の原子炉において使用されろ燃料集合
体の一例として第８図および第９図に示すものか知られ
ている。``Prior Art'' As an example of a fuel assembly used in a nuclear reactor such as a pressurized water type light water reactor, the one shown in FIGS. 8 and 9 is known.
これらの図において符号１および２は上下方向に離間し
て対向配置された上部ノズルおよび下部ノズルを示し、
これら上部ノズル１と下部ノズル２との間には、複数の
制御棒案内管３が渡されて固定されている。これら制御
棒案内管３の中途部には、複数の支持格子４が上下方向
に互いに離間して取り付けられている。゛
そして、各支持格子４の格子空間５を形成する壁部には
第９図に示すように、燃料棒６を支持するためのデイン
プル７とスプリング８とが互いに対向して形成されてお
り、格子空間５に挿通された燃料棒６はスプリング８に
よりデインプル７に押圧されて支持されている。In these figures, numerals 1 and 2 indicate an upper nozzle and a lower nozzle that are spaced apart from each other in the vertical direction and are arranged opposite to each other,
A plurality of control rod guide tubes 3 are fixed and passed between the upper nozzle 1 and the lower nozzle 2. A plurality of support grids 4 are attached to the middle portions of these control rod guide tubes 3 so as to be spaced apart from each other in the vertical direction. 9, dimples 7 and springs 8 for supporting the fuel rods 6 are formed facing each other on the wall forming the lattice space 5 of each support lattice 4. A fuel rod 6 inserted into the grid space 5 is supported by being pressed against the dimple 7 by a spring 8.
次に、上記構成の燃料集合体の組立方法について説明す
る。Next, a method for assembling the fuel assembly having the above configuration will be explained.
まず、制御棒案内管３に支持された支持格子４の格子空
間５に、燃料棒６をグリッパ（図示せず）により保持し
て挿通し、スプリング８によりデインプル７に抑圧固定
する。First, the fuel rods 6 are inserted into the lattice spaces 5 of the support lattice 4 supported by the control rod guide tubes 3 while being held by grippers (not shown), and are pressed and fixed to the dimples 7 by the springs 8.
そして、全ての燃料棒６を挿通し終えたならば、上部ノ
ズル１および下部ノズル２を制御棒案内管３の両端部に
それぞれ固定する。After all the fuel rods 6 have been inserted, the upper nozzle 1 and the lower nozzle 2 are fixed to both ends of the control rod guide tube 3, respectively.
「発明が解決しようとする問題点」
ところで、上記燃料集合体の組立方法にあっては、支持
格子４の格子空間５に燃料棒６を挿通する際に、燃料棒
６の外周面が、スプリング８とデインプル９との間に挾
まれるため、燃料棒６の外周部には、これらスプリング
８およびデインプル７により軸線方向に沿うスクラッチ
が発生してしまうという問題かあった。"Problems to be Solved by the Invention" By the way, in the method for assembling a fuel assembly described above, when inserting the fuel rods 6 into the lattice spaces 5 of the support lattice 4, the outer circumferential surface of the fuel rods 6 is Since the fuel rod 6 is sandwiched between the spring 8 and the dimple 9, there is a problem in that scratches along the axial direction are generated on the outer peripheral portion of the fuel rod 6 by the spring 8 and the dimple 7.
そこで、上記問題点を解消するために、燃料棒６の外周
面とスプリング８およびデインプル９との間に燃料棒６
の長手方向に長尺な薄膜状の自己潤滑性を有するポリエ
ステルフィルム等を介在させて燃料棒６を格子空間５に
挿通し、その後、このポリエステルフィルムを引き抜い
て支持格子４外に取り出す方法が考えられる。Therefore, in order to solve the above problem, the fuel rod 6 is provided between the outer circumferential surface of the fuel rod 6 and the spring 8 and dimple 9.
One idea is to insert a fuel rod 6 into the grid space 5 with a long thin self-lubricating polyester film interposed in the longitudinal direction, and then pull out the polyester film and take it out of the support grid 4. It will be done.
ところが、このような方法では、燃料棒６を格子空間５
に挿通ずる際、あるいはポリエステルフィルムを取り外
す際に、ポリエステルフィルムが破断して支持格子内に
残存する可能性がある。またポリエステルフィルムが破
断しないように、その厚さを厚くすると、このポリエス
テルフィルムにより上記スプリング８が必要以上に押圧
され、そのスプリング特性が変化して燃料棒６の保持力
が低下する可能性があるという問題が生じる。However, in such a method, the fuel rods 6 are placed in the lattice space 5.
During insertion or removal of the polyester film, it is possible for the polyester film to break and remain within the support grid. Furthermore, if the thickness of the polyester film is increased to prevent it from breaking, the polyester film will press the spring 8 more than necessary, which may change the spring characteristics and reduce the holding force of the fuel rod 6. A problem arises.
一方、ポリエステルより乙格段に強度の大きいステンレ
ス鋼等の金属薄膜を使用することも考えられるが、この
場合、燃料棒６と金属薄膜との間でやはりスクラッチが
発生するという問題が生じる。On the other hand, it is also conceivable to use a metal thin film made of stainless steel or the like, which has much higher strength than polyester, but in this case, the problem of scratches occurring between the fuel rod 6 and the metal thin film still arises.
この発明は上記問題点を解決することを目的としている
。This invention aims to solve the above problems.
「問題点を解決するための手段」
この発明の核燃料集合体組立方法は、支持格子の格子空
間に挿通され、格子空間を画成する壁部に形成された支
持部により支持格子に支持固定される燃料棒を、その外
周面と支持部との間に燃料棒の長手方向に長尺な薄膜状
のスペーサを介在させて格子空間に挿通ずる工程と、こ
の工程の後、スペーサを支持格子外に取り出す工程とを
有してなり、上記スペーサが自己潤滑性を有する樹脂薄
膜と、金属薄膜とからなる少なくとも２層以上の構造を
なし、かつ上記スペーサの少なくとも上記支持部に接す
る側が樹脂薄膜からなることを特徴としている。"Means for solving the problem" The method for assembling a nuclear fuel assembly of the present invention is such that the nuclear fuel assembly is inserted into the lattice space of the support lattice, and is supported and fixed to the support lattice by the support part formed on the wall part defining the lattice space. A process of inserting a fuel rod into a lattice space with a long thin film spacer interposed in the longitudinal direction of the fuel rod between the outer peripheral surface of the fuel rod and the support part, and after this process, inserting the spacer outside the support lattice. the spacer has a structure of at least two layers consisting of a self-lubricating resin thin film and a metal thin film, and at least the side of the spacer in contact with the supporting portion is made of a resin thin film. It is characterized by becoming.
「作用 」
この発明の核燃料集合体組立方法にあっては、核燃料集
合体を組み立てるに際し、支持格子の格子空間に燃料棒
をその外周面と、この燃料棒を支持固定支持部との間に
薄膜状のスペーサを介在させて挿通した後、このスペー
サを引き抜くようにしたので、燃料棒の外周面と支持部
とが直接摺接ずろことがなく、しかもスペーサの少なく
とも支持部に接する側に形成された樹脂薄膜の自己潤滑
性によりスペーサが支持部と燃料棒との間でスムーズに
滑るため燃料棒の外周面へのスクラッチの発生を防止す
ることができる。さらに、金属薄膜によりスペーサの引
張強度が高められているので、スペーサが破断すること
がない。"Function" In the method for assembling a nuclear fuel assembly of the present invention, when assembling a nuclear fuel assembly, a thin film is formed between the outer peripheral surface of the fuel rod in the lattice space of the support lattice and the fixed support part that supports the fuel rod. Since the spacer is inserted through the fuel rod with a shaped spacer interposed therebetween and then pulled out, the outer circumferential surface of the fuel rod and the support part do not come into direct sliding contact with each other, and moreover, the spacer is formed at least on the side that contacts the support part. Due to the self-lubricating property of the thin resin film, the spacer slides smoothly between the support portion and the fuel rod, thereby preventing scratches from occurring on the outer peripheral surface of the fuel rod. Furthermore, since the tensile strength of the spacer is increased by the metal thin film, the spacer will not break.
「実施例」
以下この発明の核燃料集合体組立方法の一実施例を第１
図ないし第３図を参照して説明する。``Example'' Hereinafter, a first example of the method for assembling a nuclear fuel assembly of the present invention will be described.
This will be explained with reference to FIGS.
まず、この発明の核燃料集合体組立方法を説明する前に
、この組立方法に使用されるスペーサについて説明する
。First, before explaining the nuclear fuel assembly assembly method of the present invention, the spacer used in this assembly method will be explained.
すなわち、第１図において符号！０はスペーサを示す。That is, in FIG. 1, the symbol ! 0 indicates a spacer.
このスペーサＩＯは燃料棒６の長手方向にその全長に渡
って延びる長方形状の薄膜を四角筒状に形成したもので
ある。The spacer IO is a rectangular thin film extending over the entire length in the longitudinal direction of the fuel rod 6 and formed into a square tube shape.
上記スペーサＩＯは第２図に示すように、３層構造にな
っており、その表裏部はニトロセルロースからなる自己
潤滑性を有する樹脂薄膜（膜厚：ｌＯμＪＥ）１１．１
２により形成されていると共に１、これら樹脂薄膜１１
．１２の間には、ＳＯ９からなる金属薄膜（膜厚：３０
μＮ）１３が形成されている。このようなスペーサ１０
はその表裏部と燃料棒６との間の摩擦係数が金属薄膜１
３単体と燃料棒との間のそれより小さく、かつ引張強度
がニトロセルロースのみからなる薄膜より高いものであ
る。As shown in Fig. 2, the spacer IO has a three-layer structure, and its front and back surfaces are covered with a self-lubricating resin thin film made of nitrocellulose (thickness: lOμJE) 11.1
2 and 1, these resin thin films 11
．． Between 12 and 12, a metal thin film (thickness: 30
μN) 13 is formed. Spacer 10 like this
The coefficient of friction between the front and back parts of the fuel rod 6 is the metal thin film 1.
3 is smaller than that between a simple substance and a fuel rod, and its tensile strength is higher than that of a thin film made only of nitrocellulose.
また、上記スペーサ１０は、これを格子空間５に挿入す
る際１ミ、このスペーサＩＯがデインプル７およびスプ
リング８と干渉して変形、さらには破損して、本来のス
ペーサ１０の機能が発揮できなくなることを防止するた
めに、ス、ペーサｌＯとデインプル７およびスプリング
８との間に物理的にギャップが生じるように、デインプ
ル７とこれに対向するスプリング８との間の最短距離よ
りも短い一辺の長さを有する矩形状に形成され、かつ各
辺の長さの合計が燃料棒６の外周の長さより長く設定さ
れたものである。Further, when the spacer 10 is inserted into the lattice space 5, the spacer IO interferes with the dimple 7 and the spring 8, causing deformation and even damage, making it impossible for the spacer 10 to perform its original function. In order to prevent this, one side is shorter than the shortest distance between the dimple 7 and the opposing spring 8 so that a physical gap is created between the spacer IO and the dimple 7 and the spring 8. The fuel rod 6 is formed into a rectangular shape having a long length, and the total length of each side is set to be longer than the length of the outer circumference of the fuel rod 6.
次に、上記スペーサ１０を用いた核燃料集合体組立方法
を説明する。Next, a method of assembling a nuclear fuel assembly using the spacer 10 will be explained.
まず、制御棒案内管３に支持された各支持格子４の同一
軸線上にある格子空間５に上記四角筒状のスペーサｌＯ
を挿通する。First, the square cylindrical spacer lO is placed in the grid space 5 on the same axis of each support grid 4 supported by the control rod guide tube 3.
Insert.
その後、このスペーサ１０内に燃料棒６をグリッパ（図
示せず）により保持して挿通する。この状態において、
燃料棒６の外周面には第２図に示すように、スペーサＩ
Ｏを介してスプリング８およびデインプル７が圧接して
おり、これにより燃料棒６が支持格子４に支持固定され
ている。Thereafter, the fuel rod 6 is inserted into the spacer 10 while being held by a gripper (not shown). In this state,
As shown in FIG. 2, a spacer I is provided on the outer peripheral surface of the fuel rod 6.
The spring 8 and the dimple 7 are in pressure contact with each other through O, thereby supporting and fixing the fuel rod 6 to the support grid 4.
そして、燃料棒６を挿通したならば、燃料棒６の端部を
押え部材（図示せず）により挿通方向に押えた状態にし
て、第３図に示すように、スペーサ１０を燃料棒６の挿
通方向と逆方向に引き抜き、支持格子４外に取り出す。Once the fuel rod 6 is inserted, the end of the fuel rod 6 is held down in the insertion direction by a holding member (not shown), and the spacer 10 is inserted into the fuel rod 6 as shown in FIG. Pull it out in the opposite direction to the insertion direction and take it out of the support grid 4.
この時、上記デインプル７、スプリング８およびこれら
に押圧された燃料棒６の外周面がスペーサ１０の表裏部
を相対的に摺動するが、これらスペーサ１０の表裏部は
自己潤滑性を有する樹脂薄膜１１．１２により形成され
ており、しかも樹脂薄膜１１．１２の間には金属薄膜■
３が形成されて引張強度が高いので、スペーサＩＯを破
断させることなくスムーズに引き抜くことができる。At this time, the dimple 7, the spring 8, and the outer peripheral surface of the fuel rod 6 pressed by these slide relatively on the front and back sides of the spacer 10, but the front and back sides of the spacer 10 are covered with a resin thin film having self-lubricating properties. 11.12, and between the resin thin films 11.12 and 11.12, there is a metal thin film ■
3 and has high tensile strength, the spacer IO can be pulled out smoothly without breaking.
以下、同様にして支持格子４の格子空間５にスペーサ１
０を介在させて燃料棒６を挿通し、このスペーサ１０を
引き抜く。Thereafter, spacers 1 are placed in the lattice spaces 5 of the support lattice 4 in the same manner.
The fuel rod 6 is inserted with the spacer 0 interposed therebetween, and the spacer 10 is pulled out.
そして、全ての燃料棒６を挿通し終えたならば、上部ノ
ズルｌおよび下部ノズル２を制御棒案内管３の両端部に
それぞれ固定することにより核燃料集合体の組立を完了
する。After all the fuel rods 6 have been inserted, the upper nozzle 1 and the lower nozzle 2 are fixed to both ends of the control rod guide tube 3, thereby completing the assembly of the nuclear fuel assembly.
上記核燃料集合体組立方法によれば、支持格子４の格子
空間５に燃料棒６をその、外周面とデインプル７および
スプリング８との間にスペーサＩＯを介在さ仕て挿通し
た後、スペーサｌＯを引き抜くようにしたので、燃料棒
６の外周面とデインプル７およびスプリング８等の金属
面とが直接摺接することがない。よって、燃料棒６の外
周面へのスクラッチの発生を防止することができる。According to the nuclear fuel assembly assembly method described above, after the fuel rods 6 are inserted into the lattice space 5 of the support lattice 4 with the spacer IO interposed between the outer peripheral surface and the dimple 7 and the spring 8, the spacer IO is inserted. Since the fuel rods 6 are pulled out, the outer circumferential surface of the fuel rods 6 does not come into direct sliding contact with metal surfaces such as the dimples 7 and the springs 8. Therefore, the occurrence of scratches on the outer peripheral surface of the fuel rod 6 can be prevented.
しかも、スペーサ１０がその表裏部に形成された自己潤
滑性を有する樹脂薄膜１１．１２とこれらの間に形成さ
れた金属薄膜１３とによる３層構造となっているので、
その自己潤滑性によりスペーサＩＯをスムーズに引き抜
くことができると共に、金属薄膜１３により引張強度が
高められているので、スペーサｌＯが破断することがな
い。Moreover, since the spacer 10 has a three-layer structure consisting of the self-lubricating resin thin films 11 and 12 formed on the front and back sides of the spacer 10 and the metal thin film 13 formed between them,
Its self-lubricity allows the spacer IO to be pulled out smoothly, and since the tensile strength is increased by the metal thin film 13, the spacer IO will not break.
さらに、樹脂薄膜のみで形成されたスペーサの引張強度
を高めるにはその厚さを厚くすればよいが、十分な引張
強度を得る厚さにすると、このスペーサによりスプリン
グ８が押圧されてそのスプリング特性が変化して燃料棒
６の保持力が低下ずろ可能性があるが、上記スペーサ１
０ではその内部に金属薄膜１３を設けることによりその
引張強度を高めたので、樹脂薄膜のみで形成されたスペ
ーサに比べ格段にその厚さを薄くすることができ、よっ
てスプリング特性が変化して燃料棒６の保持力が低下す
ることがない。Furthermore, in order to increase the tensile strength of a spacer formed only of a thin resin film, it is sufficient to increase its thickness, but if the thickness is increased to obtain sufficient tensile strength, the spring 8 will be pressed by this spacer, resulting in its spring characteristics. There is a possibility that the holding force of the fuel rod 6 will decrease due to the change in the spacer 1.
In 0, the tensile strength was increased by providing a metal thin film 13 inside the spacer, so the thickness could be made much thinner than a spacer made only of a resin thin film, which changed the spring characteristics and increased the fuel The holding force of the rod 6 does not decrease.
なお、上記実施例では自己潤滑性を有する樹脂としてニ
トロセルロースを用いたが、これに限ることなくアクリ
ル酸や酢酸ビニル等のハロゲンを含まない樹脂を用いて
もよい。In the above embodiments, nitrocellulose was used as the self-lubricating resin, but the present invention is not limited to this, and halogen-free resins such as acrylic acid and vinyl acetate may also be used.
また、金属薄膜１３の素材としてＳＵＳを用いたが、チ
タン、ニッケル、クロム等を用いてもよい。Further, although SUS is used as the material for the metal thin film 13, titanium, nickel, chromium, etc. may also be used.
さらに、スペーサ１０を３層構造としたが、その厚さお
よび引張強度を考慮して、少なくとも燃料棒６との接触
側に自己潤滑性を有する樹脂薄膜を形成し、かつ少なく
とも１層以上の金属薄膜を形成すれば、２層以上の多層
構造としてもよい。Furthermore, although the spacer 10 has a three-layer structure, in consideration of its thickness and tensile strength, a self-lubricating resin thin film is formed at least on the side in contact with the fuel rods 6, and at least one layer of metal is formed. If a thin film is formed, it may have a multilayer structure of two or more layers.
加えて、スペーサ１０を四角筒状にしたが、第４図ない
し第６図にそれぞれ示すように、円筒状あるいは多角筒
状等のあらゆる種類の筒状にしてもよく、さらには帯状
にしてデインプル７およびスプリング８と燃料棒６の外
周面との接する部分に燃料棒の全長に渡って介在させる
ようにしてもよい。In addition, although the spacer 10 is made into a rectangular tube shape, it may be made into any kind of tube shape such as a cylindrical shape or a polygonal tube shape, as shown in FIGS. 7 and the spring 8 and the outer circumferential surface of the fuel rod 6 may be interposed over the entire length of the fuel rod.
また、支持格子４の格子空間５にスペーサ１０を挿通し
た後、燃料棒６を挿通したが、予め燃料棒６の外周をス
ペーサＩＯにより覆い、このスペーサ１０に覆われた燃
料棒６を挿通してもよい。In addition, after inserting the spacer 10 into the grid space 5 of the support grid 4, the fuel rod 6 was inserted. However, the outer periphery of the fuel rod 6 was covered with the spacer IO in advance, and the fuel rod 6 covered with the spacer 10 was inserted. You can.
「発明の効果」
以上説明したように、この発明の核燃料集合体組立方法
によれば、支持格子の格子空間に燃料棒をその外周面と
、格子空間を画成する壁部に形成された支持部との間に
薄膜状のスペーサを介在させて挿通した後、このスペー
サを引き抜くようにしたので、燃料棒の外周面と支持部
とが直接摺接することがなく、しかもスペーサの少なく
とも支持部に接する側に形成された樹脂薄膜の自己潤滑
性によりスペーサが支持部と燃料棒との間でスムーズに
滑るため燃料棒の外周面へのスクラッチの発生を防止す
ることができる。"Effects of the Invention" As explained above, according to the method for assembling a nuclear fuel assembly of the present invention, the fuel rods are placed in the lattice space of the support lattice on the outer peripheral surface thereof and the support formed on the wall portion defining the lattice space. Since the spacer is inserted through the spacer with a thin film spacer interposed between the spacer and the support part, the spacer is pulled out, so that the outer peripheral surface of the fuel rod and the support part do not come into direct sliding contact, and at least the support part of the spacer Due to the self-lubricating property of the resin thin film formed on the contacting side, the spacer slides smoothly between the support portion and the fuel rod, thereby making it possible to prevent scratches from occurring on the outer circumferential surface of the fuel rod.
さらに、金属薄膜によりスペーサの引張強度が高められ
ているので、スペーサが破断することがない。Furthermore, since the tensile strength of the spacer is increased by the metal thin film, the spacer will not break.
第１図ないし第３図はこの発明の核燃料集合体組立方法
の一実施例を示すものであり、第１図は支持格子にスペ
ーサおよび燃料棒を挿通している状態を示す概略図、第
２図は支持格子の格子空間にスペーサおよび燃料棒が挿
通された状態を示す要部の断面図、第３図は支持格子か
らスペーサを引き抜いている状態を示す概略図、第４図
ないし第７図はそれぞれスペーサの変形例を示す概略図
、第８図は核燃料集合体の正面図、第９図は第８図に示
す支持格子の要部の平面図である。
４・・・・・・支持格子、５・・・・・・格子空間、６
・・・・・・燃料棒、７・・・・・・デインプル（支持
部）、８・・・・・・スプリング（支持部）、１０・・
・・・・スペーサ、１１．１２・・・・・・樹脂薄膜、
１３・・・・・・金属薄膜。1 to 3 show an embodiment of the method for assembling a nuclear fuel assembly according to the present invention, and FIG. 1 is a schematic diagram showing a state in which spacers and fuel rods are inserted into a support grid, and FIG. The figure is a sectional view of the main part showing a state in which a spacer and fuel rods are inserted into the lattice space of the support grid, FIG. 3 is a schematic diagram showing a state in which the spacer is pulled out from the support grid, and FIGS. 4 to 7 8 is a front view of a nuclear fuel assembly, and FIG. 9 is a plan view of a main part of the support grid shown in FIG. 8. 4... Support grid, 5... Grid space, 6
... Fuel rod, 7 ... Dimple (support part), 8 ... Spring (support part), 10 ...
...Spacer, 11.12...Resin thin film, 13...Metal thin film.
Claims (1)
画成する壁部に形成された支持部により上記燃料棒を上
記支持格子に支持固定する核燃料集合体組立方法におい
て、 上記燃料棒を、その外周面と上記支持部との間に上記燃
料棒の長手方向に長尺な薄膜状のスペーサを介在させて
上記格子空間に挿通する工程と、この工程の後、上記ス
ペーサを上記支持格子外に取り出す工程とを有してなり
、上記スペーサが自己潤滑性を有する樹脂薄膜と、金属
薄膜とからなる少なくとも２層以上の構造をなし、かつ
上記スペーサの少なくとも上記支持部に接する側が上記
樹脂薄膜からなることを特徴とする核燃料集合体組立方
法。[Claims] A method for assembling a nuclear fuel assembly in which a fuel rod is inserted into a lattice space of a support lattice, and the fuel rod is supported and fixed to the support lattice by a support portion formed on a wall defining the lattice space. a step of inserting the fuel rod into the lattice space with a longitudinally elongated thin film spacer interposed between the outer circumferential surface of the fuel rod and the support portion; and after this step, taking out the spacer outside the support grid, the spacer has a structure of at least two layers consisting of a self-lubricating resin thin film and a metal thin film, and at least the support of the spacer. A method for assembling a nuclear fuel assembly, characterized in that the side in contact with the part is made of the resin thin film described above.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62270540A JPH0660956B2 (en) | 1987-10-27 | 1987-10-27 | Nuclear fuel assembly assembling method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62270540A JPH0660956B2 (en) | 1987-10-27 | 1987-10-27 | Nuclear fuel assembly assembling method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01113699A true JPH01113699A (en) | 1989-05-02 |
| JPH0660956B2 JPH0660956B2 (en) | 1994-08-10 |
Family
ID=17487616
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62270540A Expired - Lifetime JPH0660956B2 (en) | 1987-10-27 | 1987-10-27 | Nuclear fuel assembly assembling method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0660956B2 (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01282497A (en) * | 1988-05-09 | 1989-11-14 | Mitsubishi Nuclear Fuel Co Ltd | Assembling of fuel assembly |
| US5028382A (en) * | 1990-01-24 | 1991-07-02 | General Electric Company | Scratch preventing method of assembling nuclear fuel bundles, and the assembly |
| US5533077A (en) * | 1993-10-25 | 1996-07-02 | General Electric Company | Method for preventing scratches on fuel rods during fuel bundle assembly |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5311294A (en) * | 1976-07-17 | 1978-02-01 | Genshi Nenryo Kogyo | Method of assembling reactor fuel assembly |
-
1987
- 1987-10-27 JP JP62270540A patent/JPH0660956B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5311294A (en) * | 1976-07-17 | 1978-02-01 | Genshi Nenryo Kogyo | Method of assembling reactor fuel assembly |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01282497A (en) * | 1988-05-09 | 1989-11-14 | Mitsubishi Nuclear Fuel Co Ltd | Assembling of fuel assembly |
| US5028382A (en) * | 1990-01-24 | 1991-07-02 | General Electric Company | Scratch preventing method of assembling nuclear fuel bundles, and the assembly |
| US5533077A (en) * | 1993-10-25 | 1996-07-02 | General Electric Company | Method for preventing scratches on fuel rods during fuel bundle assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0660956B2 (en) | 1994-08-10 |
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