JPS6137594B2 - - Google Patents
Info
- Publication number
- JPS6137594B2 JPS6137594B2 JP58083163A JP8316383A JPS6137594B2 JP S6137594 B2 JPS6137594 B2 JP S6137594B2 JP 58083163 A JP58083163 A JP 58083163A JP 8316383 A JP8316383 A JP 8316383A JP S6137594 B2 JPS6137594 B2 JP S6137594B2
- Authority
- JP
- Japan
- Prior art keywords
- absorbing material
- neutron absorbing
- tube
- neutron
- rectangular
- 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.)
- Expired
Links
- 239000011358 absorbing material Substances 0.000 claims description 26
- 239000000446 fuel Substances 0.000 claims description 15
- 238000004519 manufacturing process Methods 0.000 claims description 11
- 238000003860 storage Methods 0.000 claims description 8
- 238000003466 welding Methods 0.000 claims description 5
- 239000000463 material Substances 0.000 claims description 3
- 238000000034 method Methods 0.000 claims description 2
- 229910001220 stainless steel Inorganic materials 0.000 claims 2
- 239000010935 stainless steel Substances 0.000 claims 2
- 239000006096 absorbing agent Substances 0.000 claims 1
- 230000000712 assembly Effects 0.000 claims 1
- 238000000429 assembly Methods 0.000 claims 1
- 125000006850 spacer group Chemical group 0.000 description 5
- 230000000694 effects Effects 0.000 description 3
- 239000012744 reinforcing agent Substances 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 2
- 230000003014 reinforcing effect Effects 0.000 description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 description 2
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
Description
【発明の詳細な説明】
本発明は原子炉用燃料貯蔵ラツクの製造方法に
関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method of manufacturing a fuel storage rack for a nuclear reactor.
原子力プラントにおいては、原子炉炉心から取
出された使用済燃料は、再処理するまでの間一時
保管される。近年使用済燃料貯蔵プール（以下プ
ールと称す）内のスペースを有効に利用するた
め、貯蔵燃料間の間隔を狭くする改良がなされて
おり、この思想に基づいたラツクを高密度ラツク
と称している。ラツクは燃料が相互間の影響によ
り臨界に達しない構造にする必要があり、燃料間
の間隔を短くするために燃料間に中性子吸収材を
入れている。又、ラツクは燃料を貯蔵するので、
耐震的に重要な機器であり、その強度は十分でな
ければならない。ラツクはその組立性が良いこと
から、あらかじめ作られた角筒からなつており、
この角筒は強度部材と中性子吸収材からなつてい
る。 In nuclear power plants, spent fuel removed from the reactor core is temporarily stored until it is reprocessed. In recent years, in order to effectively utilize the space in spent fuel storage pools (hereinafter referred to as pools), improvements have been made to narrow the spacing between stored fuels, and racks based on this idea are called high-density racks. . The rack must have a structure in which the fuels do not reach criticality due to mutual influence, and a neutron absorbing material is inserted between the fuels to shorten the distance between the fuels. Also, since racks store fuel,
It is an important piece of equipment for earthquake resistance, and its strength must be sufficient. Because Ratsuku is easy to assemble, it is made of pre-made square tubes.
This rectangular tube consists of a strength member and a neutron absorbing material.
第１図はこの種の高密度ラツクの例であり、角
筒１を集合させて上部補強材２、中間補強材３，
４、ベース５により一体のラツクとしたものであ
る。第２図はこのラツクの角筒１の断面図、第３
図は平面図であり、角筒は外筒６、内筒７、中性
子吸収材８、スペーサー９，１０よりなつてい
る。 Figure 1 shows an example of this type of high-density rack, in which rectangular tubes 1 are assembled to form an upper reinforcing member 2, an intermediate reinforcing member 3,
4. The base 5 makes it easy to use. Figure 2 is a sectional view of the rectangular tube 1 of this rack;
The figure is a plan view, and the rectangular tube consists of an outer tube 6, an inner tube 7, a neutron absorbing material 8, and spacers 9 and 10.
従来の中性子吸収材と強度部材を併用している
角筒を用いた原子炉用燃料貯蔵ラツクは、その角
筒の４面に中性子吸収材を用いているため、角筒
を内筒と外筒から構成する必要があり、内筒と外
筒の間に中性子吸収材を入れる製作方法がとられ
ていた。この方法はそれぞれの角筒の製作公差が
厳しくなり製作性が悪く角筒の上、下端でシール
溶接が必要となり、又重量も重くなるという欠点
がある。 Conventional nuclear reactor fuel storage racks using square tubes that use both neutron absorbing material and strength members use neutron absorbing materials on four sides of the square tubes, so the square tubes can be used as inner and outer tubes. The manufacturing method used was to insert a neutron absorbing material between the inner cylinder and the outer cylinder. This method has the disadvantage that manufacturing tolerances for each rectangular tube are strict, the manufacturing efficiency is poor, seal welding is required at the top and bottom ends of the rectangular tube, and the weight is also increased.
本発明の目的は、角筒の４面のうち２面のみに
中性子吸収材を入れ中性子吸収材を有する面が重
ならないように角筒を配列し燃料の未臨界を保つ
と共に角筒の製作性を良好にし、さらに重量の軽
減を計り得る製造方法を提供するものである。 The purpose of the present invention is to arrange the square tubes so that only two of the four sides of the square tubes are provided with neutron absorbing material so that the surfaces having the neutron absorbing materials do not overlap, thereby maintaining the subcriticality of the fuel and improving the manufacturing efficiency of the square tubes. The purpose of the present invention is to provide a manufacturing method that can improve the quality and further reduce the weight.
第４図、第５図に本発明によつて作られた角筒
の断面図、平面図を示す。角筒は、相対する辺に
中性子吸収材を有し、筒１１、側板１２、中性子
吸収材１３、スペーサー１４からなる。この構造
により、角筒は従来のような内筒と外筒の２つの
筒を用いる必要がなくなる。 FIGS. 4 and 5 show a sectional view and a plan view of a rectangular tube made according to the present invention. The rectangular tube has a neutron absorbing material on opposing sides, and consists of a tube 11, a side plate 12, a neutron absorbing material 13, and a spacer 14. This structure eliminates the need for the square tube to use two tubes, an inner tube and an outer tube, as in the conventional case.
第５図は、角筒の製造方法を示すもので中性子
吸収材を相対する２面のみに有することにより、
中性子吸収材１３を有していない２面の場所１５
で突合わせて溶接して、角筒を製作するものであ
り、本製造方法では中性子吸収材の、溶接による
熱影響等を考慮する必要がなく良好な製品を製造
することができる。 Figure 5 shows a method of manufacturing a rectangular tube, and by having neutron absorbing material only on two opposing sides,
Location 15 on two sides that does not have neutron absorbing material 13
The neutron absorbing material is butted and welded to produce a rectangular tube, and this manufacturing method does not require consideration of the thermal effects of welding on the neutron absorbing material, making it possible to manufacture a good product.
本発明の角筒を用いた原子炉用燃料貯蔵ラツク
の平面図を第６図に示す。角筒をこのように配列
することにより中性子吸収材は各燃料間にはいつ
ており、従つて角筒の２面のみに中性子材を入れ
ることによつて燃料の未臨界を保つことが可能と
なる。 A plan view of a fuel storage rack for a nuclear reactor using the rectangular tube of the present invention is shown in FIG. By arranging the rectangular tubes in this way, the neutron absorbing material is placed between each fuel, and by putting neutron material on only two sides of the rectangular tubes, it is possible to maintain the subcriticality of the fuel. Become.
本発明により次の効果が生ずる。 The present invention provides the following effects.
(1) 原子炉用燃料貯蔵ラツクを構成する角筒の２
面のみに中性子吸収材を用いることにより燃料
の未臨界を保つことができる。(1) Two of the rectangular tubes that make up the reactor fuel storage rack
By using neutron absorbing material only on the surface, it is possible to keep the fuel subcritical.
(2) 中性子吸収材を有する角筒を、外筒、内筒か
ら構成する必要がなくなり、製造性が良好とな
り、重量も軽減される。(2) It is no longer necessary to configure the rectangular tube with the neutron absorbing material from an outer tube and an inner tube, improving productivity and reducing weight.
(3) 角筒の相対する２面のみに中性子吸収材を用
いているため中性子吸収材を有していない２面
で突合せ溶接すれば中性子吸収材の溶接による
熱影響を考慮する必要がなく、製造性が向上す
る。(3) Since neutron absorbing material is used only on two opposing sides of the rectangular tube, if the two sides that do not have neutron absorbing material are butt welded, there is no need to consider the thermal effects of welding the neutron absorbing material. Manufacturability is improved.
第１図は従来の高密度ラツクの正面図、第２，
３図は従来の角筒の断面図、平面図、第４，５図
は本発明により製造された角筒の断面図、平面
図、第６図は本発明の角筒を用いた燃料貯蔵ラツ
クの平面図である。
１……角筒、２……上部補強剤、３……中間補
強剤、４……中間補強剤、５……ベース、６……
外筒、７……内筒、８……中性子吸収材、９……
スペーサー、１０……スペーサー、１１……筒、
１２……側板、１３……中性子吸収材、１４……
スペーサー、１５……溶接部。
Figure 1 is a front view of a conventional high-density rack;
3 is a sectional view and a plan view of a conventional rectangular tube, FIGS. 4 and 5 are a sectional view and a plan view of a rectangular tube manufactured according to the present invention, and FIG. 6 is a fuel storage rack using the rectangular tube of the present invention. FIG. 1... Square tube, 2... Upper reinforcing agent, 3... Intermediate reinforcing agent, 4... Intermediate reinforcing agent, 5... Base, 6...
Outer cylinder, 7... Inner cylinder, 8... Neutron absorbing material, 9...
Spacer, 10... Spacer, 11... Tube,
12... Side plate, 13... Neutron absorbing material, 14...
Spacer, 15...welding part.
Claims (1)
状態で整列保持するための保持部材として、中性
子吸収材と強度部材を併用してなる角筒を用いて
いる原子炉用燃料貯蔵ラツクの製造方法におい
て、中性子吸収材を二枚のステンレスの板でサン
ドウイツチとし、シール溶接後プレスでコ形に曲
げて、二つを突合せて角筒とし、前記角筒の４面
のうち２面のみに中性子吸収材を配し、中性子吸
収材を有する面が重ならないように角筒を配列す
ることを特徴とする原子炉用燃料貯蔵ラツクの製
造方法。1. Manufacture of a fuel storage rack for a nuclear reactor that uses square tubes made of a combination of neutron absorbing material and strength material as a holding member for holding multiple fuel assemblies in an upright position at predetermined intervals. In this method, the neutron absorbing material is sandwiched between two stainless steel plates, and after seal welding, the material is bent into a U-shape using a press, and the two are butted together to form a rectangular cylinder.The neutron absorber is sandwiched between two stainless steel plates. 1. A method of manufacturing a fuel storage rack for a nuclear reactor, comprising arranging rectangular cylinders with absorbing material so that the surfaces having the neutron absorbing material do not overlap.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58083163A JPS58213293A (en) | 1983-05-11 | 1983-05-11 | Method of making nuclear fuel storage rack |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58083163A JPS58213293A (en) | 1983-05-11 | 1983-05-11 | Method of making nuclear fuel storage rack |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58213293A JPS58213293A (en) | 1983-12-12 |
| JPS6137594B2 true JPS6137594B2 (en) | 1986-08-25 |
Family
ID=13794585
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58083163A Granted JPS58213293A (en) | 1983-05-11 | 1983-05-11 | Method of making nuclear fuel storage rack |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58213293A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2515103Y2 (en) * | 1990-04-18 | 1996-10-30 | 株式会社三英社製作所 | Mounting structure for advertising board to power distribution tower |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002372597A (en) * | 2001-06-13 | 2002-12-26 | Toshiba Corp | Manufacturing method for neutron absorber and neutron absorber manufactured thereby |
-
1983
- 1983-05-11 JP JP58083163A patent/JPS58213293A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2515103Y2 (en) * | 1990-04-18 | 1996-10-30 | 株式会社三英社製作所 | Mounting structure for advertising board to power distribution tower |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58213293A (en) | 1983-12-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP2521002B2 (en) | Swirl vanes for addition to spring metal grid spacers and methods of adding swirl vanes to spring metal grid spacers | |
| JP2008196971A (en) | Spent fuel storage rack | |
| US4288699A (en) | Storage rack for the storage of fuel elements of nuclear reactors | |
| JP2003014882A (en) | Segmenting grid rack | |
| US3753855A (en) | Modular fuel rod spacer assembly for nuclear reactor fuel assemblies | |
| US3890196A (en) | Nuclear reactor fuel element assembly spacer grid and method of making | |
| EP0220931B1 (en) | Cell for a spent nuclear fuel rack | |
| US6118838A (en) | Frame-held neutron-absorbing fuel rod assembly storage rack | |
| US4948553A (en) | Method of making a rack for the storage of spent nuclear fuel | |
| US5361288A (en) | Spacer with integral zircaloy springs | |
| US4115700A (en) | High density fuel storage racks | |
| JPS61186892A (en) | Nuclear reactor fuel aggregate | |
| JPS6137594B2 (en) | ||
| JP2012058155A (en) | Used fuel storage rack | |
| JP5058089B2 (en) | Spent fuel storage rack and manufacturing method thereof | |
| JP3794814B2 (en) | Rack assembly for nuclear reactor fuel assemblies | |
| JPH0580189A (en) | Used fuel storing rack and its manufacture | |
| JP3080954B1 (en) | Spent fuel storage rack | |
| JPH0535397B2 (en) | ||
| JP4043161B2 (en) | Spent fuel storage rack | |
| JP3145085B2 (en) | Spent fuel storage rack and manufacturing method thereof | |
| JP2807361B2 (en) | Spent fuel storage rack and its manufacturing method | |
| JP2939459B2 (en) | Spent fuel storage rack and its manufacturing method | |
| JPS6331836Y2 (en) | ||
| KR810000176B1 (en) | Grid lattice with sliding strap |