JPS642913B2 - - Google Patents
Info
- Publication number
- JPS642913B2 JPS642913B2 JP55155878A JP15587880A JPS642913B2 JP S642913 B2 JPS642913 B2 JP S642913B2 JP 55155878 A JP55155878 A JP 55155878A JP 15587880 A JP15587880 A JP 15587880A JP S642913 B2 JPS642913 B2 JP S642913B2
- Authority
- JP
- Japan
- Prior art keywords
- base
- fuel
- spent fuel
- rectangular
- fuel storage
- 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
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 24
- 239000002826 coolant Substances 0.000 claims 1
- 239000011800 void material Substances 0.000 claims 1
- 239000000446 fuel Substances 0.000 description 35
- 230000005855 radiation Effects 0.000 description 16
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 14
- 229910052796 boron Inorganic materials 0.000 description 14
- 239000007769 metal material Substances 0.000 description 9
- 238000003466 welding Methods 0.000 description 8
- 239000000463 material Substances 0.000 description 7
- 229910052782 aluminium Inorganic materials 0.000 description 6
- 229910052580 B4C Inorganic materials 0.000 description 5
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 4
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 229910000838 Al alloy Inorganic materials 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 229910052804 chromium Inorganic materials 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 229910052748 manganese Inorganic materials 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
- 229910052720 vanadium Inorganic materials 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 229910052726 zirconium 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
- Fuel Cell (AREA)
Description
【発明の詳細な説明】
本発明は、燃料貯蔵プール底部に据付け、原子
炉より取出した燃料を保管する使用済燃料貯蔵ラ
ツクの組立方法に係り、特に燃料を貯蔵する角筒
体を直接連結することにより剛性を持たせた使用
済燃料貯蔵ラツクの、組立方法に関する。使用済
燃料貯蔵ラツクは、燃料貯蔵プールの１角に設け
られ、原子炉内で燃焼した燃料を冷却貯蔵して、
その崩壊熱を除去するものである。しかも、燃料
の貯蔵容量を増加するために、貯蔵する燃料の間
に放射線遮蔽能力の大なる金属材料を介在させ
て、より接近した状態で燃料を貯蔵する必要があ
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for assembling a spent fuel storage rack installed at the bottom of a fuel storage pool to store fuel taken out from a nuclear reactor. The present invention relates to a method of assembling a spent fuel storage rack which is particularly rigid. The spent fuel storage rack is installed in one corner of the fuel storage pool, and cools and stores the fuel burned in the reactor.
It removes that decay heat. Moreover, in order to increase the storage capacity of fuel, it is necessary to interpose a metal material with a high radiation shielding ability between the fuels to be stored, so that the fuels can be stored closer to each other.
以下図面を参照して従来の使用済燃料貯蔵ラツ
クについて説明する。第１図は使用済燃料貯蔵ラ
ツクの概略縦断面図である。第２図は、第１図の
正面図である。燃料１０を貯蔵する角筒体１１
を、複数の連結板１２を介在させて固定してい
た。このために、角筒体１１同士は相互に変形す
るために、比較的柔なる構造であつた。柔構造の
場合、本ラツクの持つ固有周期は低下し、建屋の
固有周期と一致する傾向がある。地震時に於いて
は、本ラツクは建屋と共振し、ベース２０に過大
な地震荷重が作用し、燃料貯蔵プール３０底にあ
るラツク基礎ボルト３１に過大な引抜荷重が作用
し不安全側にある。また、従来の使用済燃料貯蔵
ラツクは、燃料１０を貯蔵する角筒体１１の間
に、より接近した状態で燃料を貯蔵するために、
放射線遮蔽能力の大きい遮蔽板１３を挿入してい
た。この際角筒体１１と、遮蔽板１３との間に、
間隙がある。このため、遮蔽板１３は、角筒体１
１とは独立して動くために、角筒体１１と遮蔽板
１３とを一つの連成系として考えた場合、固有周
期は低下し建屋の固有周期と一致する傾向があ
る。地震時に於いては、本ラツクは、建屋と共振
し本ラツクに過大な地震荷重が作用し、本ラツク
のベース２０を燃料貯蔵プール３０の底部に設け
られたラツク基礎ボルト３１に過大な引張荷重が
作用し、不安全側にある。 A conventional spent fuel storage rack will be described below with reference to the drawings. FIG. 1 is a schematic longitudinal sectional view of a spent fuel storage rack. FIG. 2 is a front view of FIG. 1. Rectangular tube body 11 that stores fuel 10
were fixed with a plurality of connecting plates 12 interposed therebetween. For this reason, the rectangular tube bodies 11 deformed each other, so they had a relatively flexible structure. In the case of flexible structures, the natural period of the rack tends to decrease and match the natural period of the building. During an earthquake, this rack resonates with the building, an excessive seismic load acts on the base 20, and an excessive pulling load acts on the rack foundation bolts 31 at the bottom of the fuel storage pool 30, making it unsafe. In addition, in the conventional spent fuel storage rack, in order to store the fuel closer together between the rectangular cylinders 11 storing the fuel 10,
A shielding plate 13 with high radiation shielding ability was inserted. At this time, between the rectangular cylinder 11 and the shielding plate 13,
There is a gap. Therefore, the shielding plate 13
1, so when the rectangular cylinder 11 and the shielding plate 13 are considered as one coupled system, the natural period tends to decrease and match the natural period of the building. During an earthquake, this rack resonates with the building and an excessive seismic load acts on the rack, causing the base 20 of the rack to be subjected to an excessive tensile load on the rack foundation bolts 31 provided at the bottom of the fuel storage pool 30. is on the unsafe side.
本発明は、上述の事情に鑑みてなされたもの
で、第１の目的は、角筒体１１同士を直接連結す
ることにより、角筒体１１が独立して変形するこ
とを防ぎ、使用済燃料貯蔵ラツク全体としての剛
構造を得ることにある。第２の目的は、放射線遮
蔽能力の大なる遮蔽板１３を、燃料を貯蔵する角
筒体１１に固着することにより、あるいは角筒体
１１に放射線遮蔽能力を持たせて、遮蔽板１３を
除去することにより、角筒体１１と独立して動く
遮蔽板１３により剛性の低下を防止することにあ
る。以上により、角筒体１１と遮蔽板１３とを一
つの連成系として考えた場合、固有周期は増加
し、建屋の固有周期とは、かい離する。地震時に
おいて、本発明による使用済燃料貯蔵ラツクは、
建屋とは共振しないので、本ラツクに過大な地震
荷重が作用することはない。従つて、本ラツクの
根元にあるラツク基礎ボルトに過大な引張荷重が
作用することもなく、安全側になる。 The present invention has been made in view of the above-mentioned circumstances, and the first object is to prevent the rectangular cylinders 11 from being deformed independently by directly connecting the rectangular cylinders 11 to each other, and to prevent spent fuel from being deformed. The aim is to obtain a rigid structure for the storage rack as a whole. The second purpose is to remove the shielding plate 13 by fixing the shielding plate 13, which has a large radiation shielding ability, to the rectangular cylinder 11 that stores fuel, or by giving the rectangular cylinder 11 a radiation shielding ability. By doing so, it is possible to prevent a decrease in rigidity due to the shielding plate 13 that moves independently of the rectangular tube body 11. As described above, when the rectangular cylinder 11 and the shielding plate 13 are considered as one coupled system, the natural period increases and deviates from the natural period of the building. During an earthquake, the spent fuel storage rack according to the present invention can
Since it does not resonate with the building, excessive seismic loads will not be applied to this rack. Therefore, no excessive tensile load is applied to the rack foundation bolts at the base of the rack, making it safer.
以下一実施例の図面を参照して、本発明につい
て説明する。第３図は、本発明による使用済燃料
貯蔵ラツクの概略縦断面図である。第４図は、第
３図の概略上面図である。この図から分る様に使
用済燃料貯蔵ラツクは、燃料貯蔵プール３０内に
設置される。この燃料貯蔵プール３０には、燃料
１０からの放射線を遮蔽する水が張られる。この
様に燃料貯蔵プール３０内に設けられる使用済燃
料貯蔵ラツクは、主に角筒体１１、垂直板４０と
ベース２０とから構成される。角筒体１１は、燃
料１０を円滑に出し入れするための十分な内径を
持ち、また角管の上端には、面取り１５が施こし
てある。また、角筒体１１をベース２０上で１ピ
ツチ毎に立て、隣接する角筒体１１同士を固定す
ることにより、別のセル５０を形成する。このセ
ル５０の中にも燃料１０を貯蔵することがきる。
端部に配置された角筒体１１の側面には、角筒体
１１全長にわたつて垂直板４０を取付けて、セル
６０を形成する。勿論、このセル６０の中にも、
燃料１０を貯蔵することができる。また、燃料を
接近した状態で貯蔵しても、十分なる末臨界状態
を維持できる様に、放射線遮蔽能力の大なる金属
材料より角筒体１１は作製される。放射線遮蔽能
力のある金属材料としてステンレス鋼が使用され
る。また放射線遮蔽能力の大なる金属材料とし
て、硼素入りステンレス鋼も使用される。この場
合、硼素を0.5％まで含めることができる。更に、
硼素入りアルミニウム基合金を使用される。この
場合、必須成分として、Ｂ（硼素）を0.4〜3.0、
Mgを0.3〜2.0％およびSiを0.2〜1.8％を含み、
Fe、Co、Ni、Cr、Mn、Zr、Ti、Ｖ、Cuの１種
又は２種以上を加えたものである。 The present invention will be described below with reference to the drawings of one embodiment. FIG. 3 is a schematic longitudinal sectional view of a spent fuel storage rack according to the present invention. FIG. 4 is a schematic top view of FIG. 3. As can be seen from this figure, the spent fuel storage rack is installed within the fuel storage pool 30. This fuel storage pool 30 is filled with water that shields radiation from the fuel 10. The spent fuel storage rack provided in the fuel storage pool 30 is mainly composed of the rectangular cylinder 11, the vertical plate 40 and the base 20. The square tube body 11 has a sufficient inner diameter to allow the fuel 10 to be taken in and out smoothly, and a chamfer 15 is formed on the upper end of the square tube. Further, another cell 50 is formed by standing the rectangular cylinders 11 one pitch at a time on the base 20 and fixing adjacent rectangular cylinders 11 to each other. The fuel 10 can also be stored in this cell 50.
A vertical plate 40 is attached to the side surface of the rectangular cylinder 11 disposed at the end over the entire length of the rectangular cylinder 11 to form a cell 60. Of course, inside this cell 60,
Fuel 10 can be stored. Further, the rectangular cylinder 11 is made of a metal material with a high radiation shielding ability so that a sufficiently critical state can be maintained even if the fuel is stored close to each other. Stainless steel is used as a metal material with radiation shielding ability. Boron-containing stainless steel is also used as a metal material with great radiation shielding ability. In this case, up to 0.5% boron can be included. Furthermore,
Boron-containing aluminum-based alloy is used. In this case, as an essential component, B (boron) is 0.4 to 3.0,
Contains Mg 0.3-2.0% and Si 0.2-1.8%,
One or more of Fe, Co, Ni, Cr, Mn, Zr, Ti, V, and Cu are added.
第５図に示す様に、燃料を接近した状態で貯蔵
しても、十分なる末臨界状態を維持できる様に、
放射線遮蔽能力の大なる金属材料より成る遮蔽板
１４を、燃料１０を貯蔵する角筒体１１の外側に
溶接１６又はリベツト止め等で固着することも可
能である。この場合、遮蔽板１４は、硼素入りス
テンレス鋼より作製し、角筒体１１をステンレス
鋼より作製する。また、遮蔽板１４の材料とし
て、硼素入りアルミニウム基合金を使用する場合
は、角筒体１１の材料としては、市販されている
アルミニウム合金が使用される。更に、遮蔽板１
４の材料として、アルミニウムで被覆した炭化硼
素−アルミニウムが使用される場合は、角筒体１
１の材料として、市販されているアルミニウム合
金が使用される。アルミニウムで被覆した炭化硼
素−アルミニウムのＢ（硼素）は35〜40％まで含
入することができる。 As shown in Figure 5, even if the fuel is stored in close proximity, it is possible to maintain a sufficiently critical state.
It is also possible to fix the shielding plate 14 made of a metal material with high radiation shielding ability to the outside of the rectangular cylinder 11 storing the fuel 10 by welding 16 or riveting. In this case, the shielding plate 14 is made of boron-containing stainless steel, and the rectangular cylinder 11 is made of stainless steel. Furthermore, when a boron-containing aluminum-based alloy is used as the material for the shielding plate 14, a commercially available aluminum alloy is used as the material for the rectangular cylinder 11. Furthermore, the shielding plate 1
When boron carbide-aluminum coated with aluminum is used as the material of 4, the rectangular cylinder 1
A commercially available aluminum alloy is used as the first material. Boron carbide-aluminum coated with aluminum can contain up to 35-40% B (boron).
第６図に示す様に、燃料を接近した状態で貯蔵
しても、十分なる末臨界状態を維持できる様に、
放射線遮蔽能力の大なる金属材料より成る遮蔽板
１５を、燃料１０を貯蔵する角筒体１１の内側に
溶接１６又はリベツト止め等で固着することも可
能である。この場合、遮蔽板１５と角筒体１１と
の材料は上述の第５図で示した材料が使用され
る。 As shown in Figure 6, even if the fuel is stored in close proximity, it is possible to maintain a sufficiently critical state.
It is also possible to fix the shielding plate 15 made of a metal material with high radiation shielding ability to the inside of the rectangular cylinder 11 storing the fuel 10 by welding 16 or riveting. In this case, the materials used for the shielding plate 15 and the rectangular tube body 11 are those shown in FIG. 5 above.
さらに第７図に示す様に、燃料を接近した状態
で貯蔵しても、十分なる末臨界状態を維持できる
様に、放射線遮蔽能力の大なる金属材料より成る
遮蔽板１４ａ，１５ａを燃料１０を貯蔵する角筒
体１１の内外面に溶接１６又はリベツト止めで固
着する。ことも可能である。この場合、遮蔽板１
３と角筒体１１との材料は、上述の第５図で示し
た材料が使用される。 Further, as shown in FIG. 7, shielding plates 14a and 15a made of a metal material with high radiation shielding ability are used to protect the fuel 10 so that a sufficiently critical state can be maintained even when the fuel is stored in close proximity. It is fixed to the inner and outer surfaces of the rectangular cylinder 11 to be stored by welding 16 or riveting. It is also possible. In this case, the shielding plate 1
3 and the rectangular tube body 11 are made of the materials shown in FIG. 5 above.
次に、複数の角筒体１１同士及び角筒体１１と
ベース２０とを固定する工程を第８図に示し、第
９図には第８図の上面図を示す。前記の角筒体１
１は、ベース２０上に１ピツチ毎に立て、隣接す
る角筒体１１同士を溶接７０にて固定する。この
場合、角筒体１１の両隅の内、片側のみ角筒体１
１の全長にわたつて溶接７０する。同時に、ベー
ス２０上に立てた角筒体１１の下端は、１本つづ
ベース２上面に溶接８０にて固定される。前記の
様に固定した角筒体１１の周囲に順次、前記と同
様に角筒体１１を１ピツト毎に立て角筒体１１同
士及び角筒体１１とベース２０とを溶接して固定
することにより、第３図、第４図に示す様な使用
済燃料貯蔵ラツクを形成する。前記ベース２０の
詳細な縦断面図を第１０図に、その正面図を第１
１図に示す。前記のベース２０は上板２１、側板
２２と基礎板２３とから構成される。上板２１
は、燃料１０の下部を載せるための丸孔２４があ
いており、丸孔２４の中心に、前記角筒体１１の
中心を合せて、角筒体１１が固着される。また、
隣接する角筒体１１より形成されるセル５０，６
０の中心も、丸孔２４の中心と一致する。側板２
２は上板２１を支えるためのもので、上板２１に
溶接２５される。側板２２には燃料の冷却を行う
ために、冷却水が通過する冷却孔２６があいてい
る。基礎板２３は、使用済燃料貯蔵ラツクを燃料
プール３０底部に据付けるために、燃料貯蔵プー
ル３０底部より突出した基礎ボルト３１にて固定
するためのプレートである。基礎板２３は、側板
２２に溶接にて固着され、基礎板の中央部には、
基礎ボルト３１を通過するための小孔２７があい
ている。基礎板２３を通過した基礎ボルト３１
は、ナツト取扱治具（図示せず）にて、角筒体１
１とベース２０上の丸孔２４を通して、ラツク取
付ナツト３２にて固定される。 Next, FIG. 8 shows a step of fixing the plurality of rectangular tube bodies 11 to each other and the rectangular tube bodies 11 and the base 20, and FIG. 9 shows a top view of FIG. 8. Said rectangular cylinder 1
1 are erected on a base 20 at every pitch, and adjacent rectangular tube bodies 11 are fixed to each other by welding 70. In this case, only one side of both corners of the rectangular cylinder 11 is
Welding 70 is performed over the entire length of 1. At the same time, the lower ends of the rectangular cylinders 11 erected on the base 20 are fixed one by one to the upper surface of the base 2 by welding 80. Around the rectangular cylinder 11 fixed as described above, weld the rectangular cylinders 11 to each other and to the base 20 and fix the rectangular cylinders 11 in each pit in the same manner as described above. As a result, a spent fuel storage rack as shown in FIGS. 3 and 4 is formed. A detailed longitudinal sectional view of the base 20 is shown in FIG. 10, and a front view thereof is shown in FIG.
Shown in Figure 1. The base 20 is composed of a top plate 21, a side plate 22, and a base plate 23. Upper plate 21
A round hole 24 for placing the lower part of the fuel 10 is opened, and the square cylinder 11 is fixed with the center of the square cylinder 11 aligned with the center of the round hole 24. Also,
Cells 50 and 6 formed from adjacent rectangular cylinders 11
The center of 0 also coincides with the center of the round hole 24. Side plate 2
2 is for supporting the upper plate 21, and is welded 25 to the upper plate 21. The side plate 22 has cooling holes 26 through which cooling water passes in order to cool the fuel. The base plate 23 is a plate that is fixed with base bolts 31 protruding from the bottom of the fuel storage pool 30 in order to install the spent fuel storage rack on the bottom of the fuel pool 30. The base plate 23 is fixed to the side plate 22 by welding, and in the center of the base plate,
A small hole 27 is formed through which the foundation bolt 31 passes. Foundation bolt 31 passing through foundation plate 23
is a square cylinder 1 using a nut handling jig (not shown).
1 and the round hole 24 on the base 20, and are fixed with a rack mounting nut 32.
以上により構成された燃料１０を貯蔵するため
の角筒体１１を直接溶接７０にて固着するため
に、角筒体１１が独立して変形することを防ぎ、
使用済燃料ラツク全体としての剛性を増加させる
ことができる。また、放射線遮蔽能力の大なる遮
蔽板を、燃料１０を貯蔵する角筒体１１に固着す
ることにより、あるいは、角筒体１１に放射線遮
蔽能力を持たせて、遮蔽板を除去することによ
り、角筒体１１と独立して遮蔽板が動くことによ
る剛性の低下を防止することができる。燃料を接
近した状態で貯蔵しても、十分なる末臨界状態を
維持できる様に、放射線遮蔽能力の大なる硼素又
は炭化硼素が金属材料に含入される。しかしなが
ら、炭化硼素又は硼素を多量に含入すれば、放射
線遮蔽能力が著しく高まるが、強度が低下し、溶
接性が悪下する。このために、強度部材である角
筒体１１に遮蔽能力を持たせた場合は、硼素の含
量は低く押えなければならない。しかしながら、
第５図から第７図に示す様に、強度部材である角
筒体１１と遮蔽能力のある遮蔽板とに分離すれ
ば、遮蔽板に多量の硼素又は炭化硼素を含入させ
ることができ、遮蔽能力を増加させることもでき
る。しかも、強度部材である角筒体１１を堅固に
固着して使用済燃料貯蔵ラツク全体としての剛性
を増加させることができる。尚、遮蔽材は、非強
度部材であるので、多量の硼素又は炭化硼素を含
入しても、強度上の問題はない。 In order to fix the rectangular cylinder body 11 for storing the fuel 10 configured as described above by direct welding 70, the rectangular cylinder body 11 is prevented from deforming independently,
The overall rigidity of the spent fuel rack can be increased. Furthermore, by fixing a shielding plate with a large radiation shielding ability to the rectangular cylinder 11 that stores the fuel 10, or by giving the rectangular cylinder 11 a radiation shielding ability and removing the shielding plate, It is possible to prevent a decrease in rigidity due to movement of the shielding plate independently of the rectangular cylinder 11. Boron or boron carbide, which has a high radiation shielding ability, is included in the metal material so that the fuel can be stored in close proximity and still maintain a sufficiently critical state. However, if a large amount of boron carbide or boron is included, the radiation shielding ability will be significantly increased, but the strength will be reduced and the weldability will be deteriorated. For this reason, if the rectangular cylinder 11, which is a strength member, is to have a shielding ability, the boron content must be kept low. however,
As shown in FIGS. 5 to 7, by separating the rectangular cylinder 11, which is a strength member, and the shielding plate having shielding ability, the shielding plate can contain a large amount of boron or boron carbide. It can also increase your shielding ability. Furthermore, the rigidity of the spent fuel storage rack as a whole can be increased by firmly fixing the rectangular cylinder body 11, which is a strength member. Note that since the shielding material is a non-strength member, there is no problem in terms of strength even if it contains a large amount of boron or boron carbide.
上述の如く、本発明の使用済燃料貯蔵ラツク
は、全体として剛性を増し、固有周期を増加させ
ることができる。固有周期を増加した場合、建屋
の固有周期とは、かい離する。地震時に於いて、
使用済燃料貯蔵ラツクは、建屋とは共振しないの
で、本ラツクに過大な地震荷重が作用することは
ない。従つて、本ラツクの根元にあるラツク基礎
ボルトに過大なる引張荷重が作用することもなく
安全側になる。また、本ラツクは、放射線遮蔽能
力を持つ金属材料から作製された構造材を使用し
ているので、使用済燃料をより密接した状態で貯
蔵できる。従つて、一定のスペース内で、収容で
きる燃料の貯蔵能力を大幅に増加することができ
る。 As mentioned above, the spent fuel storage rack of the present invention has increased overall stiffness and can have an increased natural period. When the natural period is increased, it deviates from the natural period of the building. During an earthquake,
Since the spent fuel storage rack does not resonate with the building, excessive seismic loads will not act on the rack. Therefore, an excessive tensile load is not applied to the rack foundation bolts at the base of the rack, making it safer. Additionally, this rack uses structural members made from metal materials with radiation shielding capabilities, allowing spent fuel to be stored in closer contact. Therefore, the fuel storage capacity that can be accommodated within a given space can be significantly increased.
第１図は、従来の使用済燃料貯蔵ラツクを示す
概略縦断面図を示し、第２図は、第１図の上面
図、第３図は本発明の一実施例を示す使用済燃料
貯蔵ラツクの概略縦断面図、第４図は第３図の上
面図、第５図から第７図は、第３図の角筒体と遮
蔽板を示す縦断面図、第８図は第３図の角筒体同
士及び角筒体とベース固定する工程図、第９図は
第８図の正面図、第１０図はベースの概略縦断面
図を示し、第１１図は第１０図の上面図を示す。
１１……角筒体、１３……遮蔽板、２０……ベ
ース、４０……垂直板、５０，６０……セル。
FIG. 1 shows a schematic longitudinal cross-sectional view of a conventional spent fuel storage rack, FIG. 2 is a top view of FIG. 1, and FIG. 3 shows a spent fuel storage rack according to an embodiment of the present invention. 4 is a top view of FIG. 3, FIGS. 5 to 7 are longitudinal sectional views showing the rectangular cylinder and shielding plate of FIG. 3, and FIG. 8 is a top view of FIG. 3. Figure 9 is a front view of Figure 8, Figure 10 is a schematic vertical sectional view of the base, and Figure 11 is a top view of Figure 10. show. 11... Square cylinder, 13... Shielding plate, 20... Base, 40... Vertical plate, 50, 60... Cell.
Claims (1)
するベースと、このベース上に使用済燃料貯蔵用
の複数個の角筒体を固定配置してなる使用済燃料
貯蔵ラツクにおいて、前記角筒体の内面および外
側の内少なくとも１方の面に遮蔽板を固定し、ま
た前記角筒体はその側稜部を相互に直接に溶接し
て市松模様状に構成し、前記溶接構成され角筒体
で成す空隙部は使用済燃料を受容可能に構成した
ことを特徴とする使用済燃料貯蔵ラツク。1. A spent fuel storage rack comprising a base having a coolant flow path fixed to the bottom of the storage pool, and a plurality of rectangular cylinders for storing spent fuel fixedly arranged on the base, wherein the rectangular cylinders are fixedly arranged on the base. A shielding plate is fixed to at least one of the inner and outer surfaces of the cylindrical body, and the side ridges of the cylindrical body are directly welded to each other to form a checkered pattern, and the welded cylindrical body A spent fuel storage rack characterized in that the void formed by the above is configured to be able to receive spent fuel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55155878A JPS5780599A (en) | 1980-11-07 | 1980-11-07 | Spent fuel storage rack |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55155878A JPS5780599A (en) | 1980-11-07 | 1980-11-07 | Spent fuel storage rack |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5780599A JPS5780599A (en) | 1982-05-20 |
| JPS642913B2 true JPS642913B2 (en) | 1989-01-19 |
Family
ID=15615474
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55155878A Granted JPS5780599A (en) | 1980-11-07 | 1980-11-07 | Spent fuel storage rack |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5780599A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102737741A (en) * | 2012-07-12 | 2012-10-17 | 中广核工程有限公司 | Spent fuel storage framework of nuclear power plant |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59185698U (en) * | 1983-05-26 | 1984-12-10 | 三菱重工業株式会社 | nuclear fuel storage device |
| JPS603599A (en) * | 1983-06-21 | 1985-01-09 | 株式会社東芝 | Storage rack for used fuel |
-
1980
- 1980-11-07 JP JP55155878A patent/JPS5780599A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102737741A (en) * | 2012-07-12 | 2012-10-17 | 中广核工程有限公司 | Spent fuel storage framework of nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5780599A (en) | 1982-05-20 |
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