JPH02168197A - Fabrication of nuclear fuel assembly - Google Patents
Fabrication of nuclear fuel assemblyInfo
- Publication number
- JPH02168197A JPH02168197A JP63322115A JP32211588A JPH02168197A JP H02168197 A JPH02168197 A JP H02168197A JP 63322115 A JP63322115 A JP 63322115A JP 32211588 A JP32211588 A JP 32211588A JP H02168197 A JPH02168197 A JP H02168197A
- Authority
- JP
- Japan
- Prior art keywords
- fuel rod
- thin film
- fuel
- rod
- support member
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims description 21
- 238000004519 manufacturing process Methods 0.000 title 1
- 239000000446 fuel Substances 0.000 claims abstract description 72
- 239000010409 thin film Substances 0.000 claims abstract description 39
- 238000000034 method Methods 0.000 claims abstract description 24
- 239000004372 Polyvinyl alcohol Substances 0.000 claims abstract description 20
- 229920002451 polyvinyl alcohol Polymers 0.000 claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 9
- 239000010408 film Substances 0.000 abstract description 7
- 238000001035 drying Methods 0.000 abstract description 5
- 239000007788 liquid Substances 0.000 abstract description 2
- 229940068984 polyvinyl alcohol Drugs 0.000 abstract 2
- 235000019422 polyvinyl alcohol Nutrition 0.000 abstract 2
- 238000002791 soaking Methods 0.000 abstract 2
- 238000006073 displacement reaction Methods 0.000 description 4
- 239000002904 solvent Substances 0.000 description 4
- 230000015572 biosynthetic process Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000003780 insertion Methods 0.000 description 3
- 230000037431 insertion Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000002411 adverse Effects 0.000 description 2
- 239000007864 aqueous solution Substances 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- DKPFZGUDAPQIHT-UHFFFAOYSA-N Butyl acetate Natural products CCCCOC(C)=O DKPFZGUDAPQIHT-UHFFFAOYSA-N 0.000 description 1
- 239000000020 Nitrocellulose Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000007598 dipping method Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- FUZZWVXGSFPDMH-UHFFFAOYSA-N hexanoic acid Chemical compound CCCCCC(O)=O FUZZWVXGSFPDMH-UHFFFAOYSA-N 0.000 description 1
- 239000004615 ingredient Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229920001220 nitrocellulos Polymers 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 238000006748 scratching Methods 0.000 description 1
- 230000002393 scratching effect Effects 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 238000005507 spraying Methods 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
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は原子炉で用いられる核燃料集合体の組立方法に
関し、特に、燃料棒を支持格子に挿入する際に生じる燃
料棒表面傷の防止に関するものである。Detailed Description of the Invention [Field of Industrial Application] The present invention relates to a method for assembling a nuclear fuel assembly used in a nuclear reactor, and in particular to a method for preventing damage to the surface of fuel rods that occurs when inserting the fuel rods into a support grid. It is something.
〔従来の技術］
第３図は加圧水型原子炉に用いられる一般的な核燃料集
合体１を示している０図示するように、核燃料集合体１
は多数の細長い燃料棒２を束ねたものから成り、これら
の燃料棒２を支持するために支持格子３が長さ方向に必
要数配置されている。[Prior Art] Fig. 3 shows a general nuclear fuel assembly 1 used in a pressurized water reactor.
is made up of a bundle of a large number of elongated fuel rods 2, and in order to support these fuel rods 2, a required number of support grids 3 are arranged in the longitudinal direction.
これらの支持格子３には複数の制御棒案内管４が挿入さ
れ、各支持格子３はこれらの制御棒案内管４に固定され
ている。また、制御棒案内管４の上端及び下端にはそれ
ぞれ上部ノズル５及び下部ノズル６が取り付けられてい
る。A plurality of control rod guide tubes 4 are inserted into these support grids 3, and each support grid 3 is fixed to these control rod guide tubes 4. Furthermore, an upper nozzle 5 and a lower nozzle 6 are attached to the upper and lower ends of the control rod guide tube 4, respectively.
支持格子３は、第４図に示す如く、複数枚の金属薄板を
格子状に組み合わせて構成され、断面四角形の格子セル
フを複数画成している。燃料棒２及び制御棒案内管４は
それぞれ対応の格子セルフ内に挿入される。また、燃料
棒２が挿入される各格子セルフの壁部には、第５図及び
第６図に明示するように、剛性支持部材８及び弾性支持
部材９が設けられており、弾性支持部材９の弾性力によ
り燃料棒２が剛性支持部材８に押し付けられて保持され
るようになっている。As shown in FIG. 4, the support lattice 3 is constructed by combining a plurality of metal thin plates in a lattice shape, and defines a plurality of lattice cells each having a square cross section. The fuel rods 2 and control rod guide tubes 4 are each inserted into the corresponding grid self. Further, as shown in FIGS. 5 and 6, a rigid support member 8 and an elastic support member 9 are provided on the wall of each grid cell into which the fuel rods 2 are inserted. The fuel rod 2 is pressed and held against the rigid support member 8 by the elastic force of the fuel rod 2 .
このような構成の核燃料集合体１の組立は、まず、支持
格子３を所定間隔に配列し、これらの支持格子３の格子
セルフに制御棒案内管４を通して両者を固定し核燃料集
合体１の骨格を構成し、この後、燃料棒２を所定の格子
セルフ内に挿入することにより行われる６しかし、燃料
棒２は剛性支持部材８及び弾性支持部材９に接しながら
挿入されるために、燃料棒２の表面にはほぼ全長に亘り
引掻き傷が生ずるという問題がある。To assemble the nuclear fuel assembly 1 having such a configuration, first, the support grids 3 are arranged at predetermined intervals, and the control rod guide tubes 4 are passed through the grid self of these support grids 3 to fix both of them, and the framework of the nuclear fuel assembly 1 is assembled. 6 However, since the fuel rods 2 are inserted while contacting the rigid support member 8 and the elastic support member 9, the fuel rods are There is a problem in that the surface of No. 2 is scratched over almost its entire length.
このような核燃料集合体組立時における燃料棒表面傷を
防止する方法としては、従来から色々と考えられている
０例えば、燃料棒２を挿入する前に弾性支持部材９を撓
ませて剛性支持部材８との間隔を燃料棒２の外径よりも
広げておき、燃料棒挿入後に、弾性支持部材９を元に戻
して燃料棒２を固定する方法がある。Various methods have been considered to prevent damage to the surface of fuel rods during the assembly of nuclear fuel assemblies. 8 is wider than the outer diameter of the fuel rod 2, and after the fuel rod is inserted, the elastic support member 9 is returned to its original position to fix the fuel rod 2.
この方法は、弾性支持部材９を広い弾性領域で使用して
いる場合には適用可能であるが、変位量に余裕のない弾
性支持部材９の場合、即ち小さな変位で塑性変形する弾
性支持部材９の場合には適用できない。また、弾性支持
部材９を大きく変形することができるとしても、幾段も
の支持格子３内を全く支持部材８．９と接触することな
く燃料棒２を挿入させることは不可能であり、従って軽
微な引掻き傷は免れない。This method is applicable when the elastic support member 9 is used in a wide elastic range, but when the elastic support member 9 has no margin for displacement, that is, the elastic support member 9 is plastically deformed with a small displacement. Not applicable in the case of Further, even if the elastic support member 9 can be greatly deformed, it is impossible to insert the fuel rod 2 into the support grid 3 in multiple stages without making any contact with the support member 8.9. Scratches are inevitable.
そこで従来においては、予め燃料棒２の表面にニトロセ
ルローズの薄膜を形成し、燃料棒２を支持格子３に挿入
して核燃料集合体１を組み立てた後に溶剤でこの薄膜を
除去する方法が提案され、海外では実際に用いられてい
る。Conventionally, a method has been proposed in which a thin film of nitrocellulose is formed on the surface of the fuel rod 2 in advance, and this thin film is removed using a solvent after the fuel rod 2 is inserted into the support grid 3 and the nuclear fuel assembly 1 is assembled. , is actually used overseas.
この方法は、薄膜により燃料棒挿入時の引掻き傷を防止
するものであるが、強固な薄膜を形成するには、ブチル
アセテート等の揮発・引火性の溶剤を多量に必要とする
ため放射線管理区域内での使用となるので、安全性の面
で好ましくなく、我国ではこの方法は採用されていない
。This method uses a thin film to prevent scratches when the fuel rods are inserted, but it requires a large amount of volatile and flammable solvents such as butyl acetate to form a strong thin film, so it is not suitable for use in radiation-controlled areas. This method is not used in Japan because it is not recommended in terms of safety because it is used within the country.
また、燃料棒２の表面に薄膜を形成する方法としては、
氷の薄膜によるものが従来から知られている。In addition, as a method for forming a thin film on the surface of the fuel rod 2,
It has been known for some time that it is caused by a thin film of ice.
しかしながら、この方法では、氷膜の厚さを一定とし且
つ表面平滑度を一定レベル以上とすることは実際上極め
て困難であり、従って、弾性支持部材９のばね変位に余
裕がない場合にはこの方法は不適当である。また、氷膜
形成工程から燃料棒挿入工程までには時間がかかり、燃
料棒２の保管のための冷却設備が必要となる。更に、氷
膜は支持部材８．９との片当たりだけで剥離する可能性
が大きいという問題もある。However, with this method, it is actually extremely difficult to keep the thickness of the ice film constant and the surface smoothness above a certain level. The method is inappropriate. Furthermore, it takes time from the ice film formation step to the fuel rod insertion step, and cooling equipment for storing the fuel rods 2 is required. Furthermore, there is a problem in that the ice film is highly likely to peel off due to only one-sided contact with the support member 8.9.
［発明が解決しようとする課題］
本発明は、燃料棒表面傷の発生を防止するために燃料棒
の表面に薄膜を形成する手段を取り入れた核燃料集合体
の組立方法に係り、上述した従来技術における種々の課
題を解決することを目的とするものである。即ち、燃料
棒表面に形成される薄膜は、燃料棒を支持格子の支持部
材から十分に保護できる強度を有していなければならず
、その形成及び除去等の取扱いも容易である必要がある
。[Problems to be Solved by the Invention] The present invention relates to a method for assembling a nuclear fuel assembly that incorporates means for forming a thin film on the surface of fuel rods in order to prevent the occurrence of surface scratches on the fuel rods, and the present invention relates to a method for assembling a nuclear fuel assembly that incorporates means for forming a thin film on the surface of fuel rods in order to prevent the occurrence of surface scratches on the fuel rods. The aim is to solve various problems in the field. That is, the thin film formed on the surface of the fuel rod must have sufficient strength to protect the fuel rod from the support members of the support grid, and must be easy to handle, such as formation and removal.
また、薄膜の材料及び溶剤は、環境及びプラント設備に
対して悪影響を与えるものであってはならない。Furthermore, the thin film materials and solvents must not have a negative impact on the environment and plant equipment.
［課題を解決するための手段］
前記課題を解決するなめに、本発明は、支持格子の格子
セルに燃料棒を挿入することにより核燃料集合体を組み
立てる方法において、各燃料棒の表面に所定厚さのポリ
ビニルアルコールの薄膜を形成し、前記各燃料棒を支持
格子の対応の格子セル内に挿入して所定位置に保持し、
核燃料集合体全体を水中又は水蒸気に浸漬して前記薄膜
を溶解し除去することにより燃料棒表面に生ずる摺動傷
の防止を特徴としている。[Means for Solving the Problems] In order to solve the above problems, the present invention provides a method for assembling a nuclear fuel assembly by inserting fuel rods into lattice cells of a support grid, in which a predetermined thickness is formed on the surface of each fuel rod. forming a thin film of polyvinyl alcohol and inserting each fuel rod into a corresponding grid cell of a support grid to hold it in place;
A feature of this method is that the entire nuclear fuel assembly is immersed in water or steam to dissolve and remove the thin film, thereby preventing scratches from occurring on the surface of the fuel rods.
［作用コ
本発明によれば、ポリビニルアルコールの：３膜は強度
が高く、燃料棒を十分に保護し、挿入時における支持格
子の支持部材による引掻き傷を防止する。また、ポリビ
ニルアルコールは水溶性且つ無害であるので、薄膜の形
成及び除去を容易に、しかも安全に行うことができる。[Operations] According to the present invention, the polyvinyl alcohol 3 film is of high strength and provides sufficient protection to the fuel rods, preventing scratching by the support members of the support grid during insertion. Furthermore, since polyvinyl alcohol is water-soluble and harmless, the thin film can be formed and removed easily and safely.
［実施例］
以下、図面と共に本発明の好適な実施例について詳細に
説明する。[Embodiments] Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the drawings.
本発明による核燃料集合体の組立方法は、上述したよう
に、燃料棒の表面にポリビニルアルコールの薄膜を形成
した後に支持格子に燃料棒を挿入する点で従来のものと
異なるが、その他の工程は従来の組立方法と実質的に同
一である。よって、以下の説明では第３図〜第６図も併
せて参照されたい。As mentioned above, the method for assembling a nuclear fuel assembly according to the present invention differs from the conventional method in that the fuel rods are inserted into the support grid after forming a thin film of polyvinyl alcohol on the surface of the fuel rods, but the other steps are as follows. This is substantially the same as the conventional assembly method. Therefore, in the following description, please also refer to FIGS. 3 to 6.
まず、燃料棒２の表面にポリビニルアルコールの薄膜を
形成するために、第１図に示すように、液槽１０内のポ
リビニルアルコール水溶液１１中に燃料棒２を浸漬する
０次いで、この燃料棒２を所定の速さで引き上げつつ、
乾燥筒１２内でヒータ１３により乾燥することにより、
燃料棒２の表面に薄膜を形成する。１回の引上げによる
薄膜の厚さは、ポリビニルアルコール水溶液１１の濃度
及び燃料棒引上げ速度を適宜選択することにより調整で
きる。First, in order to form a thin film of polyvinyl alcohol on the surface of the fuel rod 2, as shown in FIG. While pulling up at a predetermined speed,
By drying with the heater 13 in the drying tube 12,
A thin film is formed on the surface of the fuel rod 2. The thickness of the thin film produced by one pulling process can be adjusted by appropriately selecting the concentration of the polyvinyl alcohol aqueous solution 11 and the fuel rod pulling rate.
才な、前記作業を繰り返し、複数層から成る薄膜を形成
することもでき、この場合には、均質でより一層強固な
薄膜が得られる。It is also possible to form a thin film consisting of multiple layers by repeating the above-mentioned process, in which case a homogeneous and even stronger thin film is obtained.
このようにして、各燃料棒２にポリビニルアルコールの
薄膜を形成したｔ麦、予め制御棒案内管４に所定の間隔
で固定された支持格子３の各格子セルフに燃料棒２を挿
入する。この際、燃料棒２は剛性支持部材８及び弾性支
持部材９に対して接触摺動し、これらにより締付は力を
受けるが、薄膜の存在により燃料棒２への直接接触は回
避される。After forming a polyvinyl alcohol thin film on each fuel rod 2 in this manner, the fuel rod 2 is inserted into each grid self of the support grid 3 which is fixed in advance to the control rod guide tube 4 at a predetermined interval. At this time, the fuel rod 2 comes into contact with and slides against the rigid support member 8 and the elastic support member 9, and is subjected to a tightening force by these, but direct contact with the fuel rod 2 is avoided due to the presence of the thin film.
実験では、９段の支持格子３を持つ核燃料集合体１の場
合、支持部材８．９による締付は力を約６ｋｇｆ、Ｆｉ
！膜の厚さを１０μ鞘とすると、薄膜上の傷深さは４μ
ｍ前後となり、燃料棒２自体は無傷であった。また、こ
の場合、燃料棒挿入による弾性支持部材９の変位量も、
薄膜無しのものに比し殆ど差がなく、燃料棒２に対する
締付は力に悪影響を与えるものでないことも確認されて
いる。In the experiment, in the case of a nuclear fuel assembly 1 having a nine-stage support grid 3, the tightening force by the support members 8.9 was approximately 6 kgf, Fi
! If the thickness of the membrane is 10μ, the scratch depth on the thin film is 4μ.
The fuel rod 2 itself was intact. In addition, in this case, the amount of displacement of the elastic support member 9 due to insertion of the fuel rod is also
It has been confirmed that there is almost no difference compared to the one without a thin film, and that tightening the fuel rod 2 does not adversely affect the force.
この後、第２図に示すように、水１４を満たした溶解槽
１５内に核燃料集合体１全体と沈め、ヒータ１６で水１
４を５０℃以上に均等に加熱して放置する。Thereafter, as shown in FIG.
4. Heat evenly to 50°C or higher and leave.
この結果、ポリビニルアルコールの薄膜は溶解し燃料棒
２から完全に除去され、表面傷のない燃料棒２を備えた
核燃料集合体１が得られる９本発明の実験では、８０℃
の温水において１〜１．５時間で１０〜２０μ鴎の薄膜
が完全に除去された。この溶解槽１５には、複数の核燃
料集合体１を同時に入れて処理することができるので、
作業効率が良く、また、ポリビニルアルコールは安全性
の高いものであるので大気開放で作業を行うことができ
る。更に、１００℃以下の温水でポリビニルアルコール
除去が可能であるので、加圧加熱設備等の必要がなく、
設備コストの低減化を図ることも可能である。As a result, the polyvinyl alcohol thin film is dissolved and completely removed from the fuel rods 2, and a nuclear fuel assembly 1 having fuel rods 2 with no surface scratches is obtained.
A thin film of 10 to 20 microns was completely removed in 1 to 1.5 hours in hot water. Since a plurality of nuclear fuel assemblies 1 can be put into the melting tank 15 and processed at the same time,
Work efficiency is good, and since polyvinyl alcohol is highly safe, work can be done in the open to the atmosphere. Furthermore, since polyvinyl alcohol can be removed with hot water of 100°C or less, there is no need for pressure heating equipment, etc.
It is also possible to reduce equipment costs.
尚、上記実施例では、ポリビニルアルコール水溶液に燃
料棒を浸漬する浸漬法により薄膜を形成することとして
いるが、薄膜は、噴霧吹付けによる等の他の適宜な方法
によっても形成することができる。In the above embodiments, the thin film is formed by a dipping method in which the fuel rod is immersed in an aqueous polyvinyl alcohol solution, but the thin film can also be formed by other suitable methods such as spraying.
［発明の効果］
以上のように、本発明によれば、薄膜の材料としてポリ
ビニルアルコールを用いているので、燃料棒表面に強固
な保護膜を形成することができ、燃料棒の無傷化を達成
することができる。[Effects of the Invention] As described above, according to the present invention, since polyvinyl alcohol is used as the thin film material, a strong protective film can be formed on the surface of the fuel rod, and the fuel rod can be made undamaged. can do.
また、ポリビニルアルコールは、不燃性であり、人体に
対して何等の影響ら与えず、しかも原子力禁止材を成分
として含んでいないので、燃料棒から完全に除去されな
くともプラント設備に悪影響を及ぼす心配もない、更に
、ポリビニルアルコールは水を溶剤として取り汲うので
、この点からも安全であり、燃料棒表面に所定厚さの薄
膜を容易に形成することができ、その除去も極めて簡単
に行うことができる。従って、本発明による核燃料集合
体の組立方法は、放射線管理区域内で安全に行い得る施
工性の高い方法である。In addition, polyvinyl alcohol is non-flammable and does not have any effect on the human body, and it does not contain nuclear-prohibited materials as ingredients, so even if it is not completely removed from the fuel rods, there is a concern that it may have an adverse effect on plant equipment. Furthermore, since polyvinyl alcohol uses water as a solvent, it is safe from this point of view as well, and a thin film of a predetermined thickness can be easily formed on the surface of the fuel rod, and its removal is also extremely easy. be able to. Therefore, the method for assembling a nuclear fuel assembly according to the present invention is a highly workable method that can be carried out safely in a radiation controlled area.
また、実験から薄膜の厚さは１０μｍ程度で良いことが
分かっているため、燃料棒挿入時に弾性支持部材に余分
な変位を与えることがなく、薄膜除去後に燃料棒の支持
力が低下する恐れもない。In addition, since experiments have shown that the thickness of the thin film is approximately 10 μm, there is no need to apply unnecessary displacement to the elastic support member when inserting the fuel rod, and there is no risk that the supporting force of the fuel rod will decrease after the thin film is removed. do not have.
第１図は本発明に従って燃料棒にポリビニルアルコール
の薄膜を形成しているところを示す概略説明図、第２図
は燃料棒からポリビニルアルコールの薄膜を除去してい
るところを示す概略説明図、第３図は核燃料集合体の全
体を示す概略正面図、第４図は第３図のＡ−Ａ線に沿っ
ての概略断面図、第５図は支持格子の構成を明瞭に示す
ための第３図のＡ−Ａ線に沿っての断面部分図、第６図
は第５図のＢ−Ｂ線に沿っての断面図である０図中、１
・・・核燃料集合体 ２・・・燃料棒３・・・支持格
子 ７・・・格子セル８・・・剛性支持部材
９・・・弾性支持部材１０・・・液槽
１１・・・ポリビニルアルコール水溶液１２・・・乾燥
筒 １４・・・水１５・・・溶解槽
１６・・・ヒータ特許出願人 三菱重工業株式会社
第１図FIG. 1 is a schematic explanatory diagram showing the formation of a polyvinyl alcohol thin film on a fuel rod according to the present invention; FIG. 2 is a schematic explanatory diagram showing the removal of the polyvinyl alcohol thin film from the fuel rod; 3 is a schematic front view showing the entire nuclear fuel assembly, FIG. 4 is a schematic sectional view taken along line A-A in FIG. 3, and FIG. 1 is a partial cross-sectional view taken along the line A-A in the figure, and FIG. 6 is a cross-sectional view taken along the line B-B in FIG.
... Nuclear fuel assembly 2 ... Fuel rod 3 ... Support lattice 7 ... Lattice cell 8 ... Rigid support member
9...Elastic support member 10...Liquid tank 11...Polyvinyl alcohol aqueous solution 12...Drying cylinder 14...Water 15...Dissolution tank
16... Heater patent applicant Mitsubishi Heavy Industries, Ltd. Figure 1
Claims (1)
料集合体を組み立てる方法において、各燃料棒の表面に
所定厚さのポリビニルアルコールの薄膜を形成し、前記
各燃料棒を支持格子の対応の格子セル内に挿入して所定
位置に保持し、核燃料集合体全体を水中に浸漬して前記
薄膜を溶解し除去することにより燃料棒表面に生ずる摺
動傷の防止を特徴とする核燃料集合体の組立方法。In a method for assembling a nuclear fuel assembly by inserting fuel rods into the grid cells of a support grid, a thin film of polyvinyl alcohol of a predetermined thickness is formed on the surface of each fuel rod, and each fuel rod is inserted into the corresponding grid cell of the support grid. Assembly of a nuclear fuel assembly characterized by preventing sliding scratches on the fuel rod surface by inserting it into a cell and holding it in a predetermined position, and immersing the entire nuclear fuel assembly in water to dissolve and remove the thin film. Method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63322115A JPH02168197A (en) | 1988-12-22 | 1988-12-22 | Fabrication of nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63322115A JPH02168197A (en) | 1988-12-22 | 1988-12-22 | Fabrication of nuclear fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02168197A true JPH02168197A (en) | 1990-06-28 |
Family
ID=18140086
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63322115A Pending JPH02168197A (en) | 1988-12-22 | 1988-12-22 | Fabrication of nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02168197A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04212098A (en) * | 1990-01-24 | 1992-08-03 | General Electric Co <Ge> | Method for preventing scratching of nuclear- fuel bundle assembly and preventing assembly |
| JP2011133481A (en) * | 2009-12-22 | 2011-07-07 | Westinghouse Electric Co Llc | Method for reducing friction and physical contact between fuel rod and support grid of nuclear fuel assembly |
| CN106935302A (en) * | 2015-12-31 | 2017-07-07 | 中核建中核燃料元件有限公司 | A kind of fuel rod surface coating method |
-
1988
- 1988-12-22 JP JP63322115A patent/JPH02168197A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04212098A (en) * | 1990-01-24 | 1992-08-03 | General Electric Co <Ge> | Method for preventing scratching of nuclear- fuel bundle assembly and preventing assembly |
| JP2011133481A (en) * | 2009-12-22 | 2011-07-07 | Westinghouse Electric Co Llc | Method for reducing friction and physical contact between fuel rod and support grid of nuclear fuel assembly |
| CN106935302A (en) * | 2015-12-31 | 2017-07-07 | 中核建中核燃料元件有限公司 | A kind of fuel rod surface coating method |
| CN106935302B (en) * | 2015-12-31 | 2019-01-08 | 中核建中核燃料元件有限公司 | A kind of fuel rod surface coating method |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| SE7708429L (en) | FUEL ELEMENT ELEMENT REPAIR PROCEDURE | |
| US3457630A (en) | Fluxless brazing of aluminum | |
| JPH02168197A (en) | Fabrication of nuclear fuel assembly | |
| US20080121248A1 (en) | Laser Decontamination of the Surface of a Profiled Part | |
| CN103184463A (en) | Acid dipping device used for nuclear rod jacketing tube and having function of preventing acid wash from leaking | |
| JPH06289171A (en) | Fuel aggregate, its fuel-rod coated pipe and reinforcement method of nuclear fuel rod | |
| US3571907A (en) | Method of cladding a metal surface | |
| JP2511578B2 (en) | Method for preventing damage due to contact of components in a bundle of nuclear fuel elements used in a nuclear reactor and a bundle of nuclear fuel elements used in a nuclear reactor | |
| JPH02268921A (en) | Method and means for sizing metal utilizing thermal expansion and contraction | |
| EP0025988B1 (en) | Braze repair method | |
| US3071178A (en) | Apparatus for controlled etching of metal | |
| JPS60239695A (en) | Nuclear fuel rod | |
| DE3236665C2 (en) | Method of assembling (assembling) a nuclear reactor fuel element | |
| EP0533097B1 (en) | Process for impregnating of a heat exchanger | |
| JPS59179791A (en) | Surface treatment of coated pipe for nuclear fuel rod | |
| JPH07198891A (en) | Method for preventing scratch to fuel rod during fuel bundle assembling | |
| US3154845A (en) | Method of fabricating a fuel element | |
| US4709848A (en) | Method of bonding | |
| CN218404414U (en) | Long-period group hole rust prevention device | |
| JPH0688888A (en) | Method of finishing atomic fuel assembly | |
| JPH02129598A (en) | Fuel storage rack | |
| Steele et al. | Summary of sodium removal and decontamination programs in the USA | |
| JPH06210448A (en) | Method for welding plate joining | |
| KR920000495B1 (en) | Element immersed in coolant of nuclear reactor | |
| FR2486541A1 (en) | LOW-FLOWING ZIRCONIUM ALLOY TUBES FOR NUCLEAR REACTORS, AND METHOD FOR MANUFACTURING THE SAME |