JPH0216318Y2 - - Google Patents
Info
- Publication number
- JPH0216318Y2 JPH0216318Y2 JP1983144465U JP14446583U JPH0216318Y2 JP H0216318 Y2 JPH0216318 Y2 JP H0216318Y2 JP 1983144465 U JP1983144465 U JP 1983144465U JP 14446583 U JP14446583 U JP 14446583U JP H0216318 Y2 JPH0216318 Y2 JP H0216318Y2
- Authority
- JP
- Japan
- Prior art keywords
- container
- fuel
- lid
- pit
- nuclear fuel
- 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 26
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 25
- 239000003758 nuclear fuel Substances 0.000 claims description 20
- 239000012530 fluid Substances 0.000 claims description 8
- 238000005070 sampling Methods 0.000 claims description 2
- 239000000446 fuel Substances 0.000 description 26
- 239000012857 radioactive material Substances 0.000 description 9
- 101150054854 POU1F1 gene Proteins 0.000 description 8
- 230000005855 radiation Effects 0.000 description 5
- 238000005253 cladding Methods 0.000 description 4
- 239000000498 cooling water Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000007547 defect Effects 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910000746 Structural steel Inorganic materials 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000010959 steel Substances 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)
- Closures For Containers (AREA)
Description
【考案の詳細な説明】
産業上の利用分野
本考案は核燃料保管容器、特に、原子炉から取
り出された使用済核燃料の中、損傷したものを収
容して使用済核燃料貯蔵ピツト内に保管するのに
好適な核燃料保管容器に関する。[Detailed description of the invention] Industrial application field The present invention is a nuclear fuel storage container, in particular, a container for storing damaged spent nuclear fuel taken out from a nuclear reactor and stored in a spent nuclear fuel storage pit. The present invention relates to a nuclear fuel storage container suitable for.
従来の技術
原子力発電プラントにおいて、原子炉から取出
された核燃料は、原子炉核納容器に隣接した燃料
取扱建屋内の使用済燃料ピツト（第１，２図の符
号１参照）で６ケ月以上冷却し、更に核燃料検査
ピツトで燃料被覆管にピンホール等の欠陥がない
ことを確認したのち再処理工場に運び出される。Conventional technology In a nuclear power plant, nuclear fuel taken out from a nuclear reactor is cooled for six months or more in a spent fuel pit (see reference numeral 1 in Figures 1 and 2) in a fuel handling building adjacent to the reactor nuclear containment vessel. After confirming that there are no pinholes or other defects in the fuel cladding in a nuclear fuel inspection pit, the fuel is transported to a reprocessing plant.
従来は、もし燃料被覆管にピンホール等が発見
されると、その核燃料は、ピンホールから放射性
物質が漏出しなくなるまで、引き続き使用済燃料
ラツク内に貯蔵していた。 Conventionally, if a pinhole or the like was found in a fuel cladding tube, the nuclear fuel was stored in a spent fuel rack until radioactive materials stopped leaking from the pinhole.
考案が解決しようとする課題
従来は燃料被覆管にピンホール等が発見された
場合に、前述の如く、その燃料を引き続き使用済
燃料ラツク（第１，２図の符号２参照）内に貯蔵
していたが、使用済燃料ラツクは密閉構造ではな
いので、このまま長期間使用済燃料ピツト内に貯
蔵しておくと、核燃料の燃料棒内放射性物質が、
ピンホール等から徐々に漏れ出て使用済燃料ピツ
ト内の核燃料の冷却兼放射線遮蔽用の水が放射性
物質に汚染されてしまい、放射線量が高くなり、
作業員への被曝線量が増える懸念があつた。Problems to be solved by the invention Conventionally, when a pinhole or the like is found in the fuel cladding tube, the fuel is stored in the spent fuel rack (see numeral 2 in Figures 1 and 2) as described above. However, since the spent fuel rack is not a sealed structure, if it is stored in the spent fuel pit for a long period of time, the radioactive materials in the nuclear fuel rods will be released.
The water that is used to cool the nuclear fuel and shield it from radiation in the spent fuel pit gradually leaks from pinholes and becomes contaminated with radioactive materials, resulting in high radiation levels.
There were concerns that the radiation doses to workers would increase.
本考案は損傷燃料からの放射性物質の漏洩を防
止した核燃料保管容器を提供することを目的とす
るものである。 The object of the present invention is to provide a nuclear fuel storage container that prevents the leakage of radioactive materials from damaged fuel.
課題を解決するための手段
損傷燃料を蓋付き密閉保管容器に収容し、損傷
燃料を収容した密閉保管容器を使用済燃料ピツト
の一隅に保管する。Means for Solving the Problems The damaged fuel is stored in a sealed storage container with a lid, and the sealed storage container containing the damaged fuel is stored in one corner of the spent fuel pit.
密閉保管容器には、容器内圧力を調整するレリ
ーフ弁と、試料水採取パイプを接続するクイツク
継手とを設ける。 The sealed storage container is equipped with a relief valve to adjust the pressure inside the container and a quick fitting to connect the sample water collection pipe.
作 用
損傷燃料を収容した密閉保管容器が放射性物質
の漏洩を防止する。密閉保管容器内の圧力が一定
限度以上に上昇又は低下すると、レリーフ弁によ
り圧力調整が行われる。クイツク継手に試料水採
取パイプを接続し、試料水を抜出して、容器内の
放射性物質の分析、監視等を行う。Effect: A closed storage container containing damaged fuel prevents leakage of radioactive materials. When the pressure inside the closed storage container rises or falls above a certain limit, the pressure is regulated by the relief valve. Connect the sample water collection pipe to the quick fitting, draw out the sample water, and analyze and monitor the radioactive materials inside the container.
実施例
本考案を図示の１実施例を参照しながら具体的
に説明する。Embodiment The present invention will be specifically described with reference to an illustrated embodiment.
第１図および第２図は、使用済燃料ピツト１内
での損傷燃料保管容器貯蔵ラツク３の取付位置を
示したものであり、第１図は部分的に省略して示
す平面図、第２図は第１図の−線に沿う断面
図である。使用済燃料ピツト１内は、その殆んど
が使用済燃料ラツク２で占められ、損傷燃料保管
容器貯蔵ラツク３は、使用済燃料ピツト１内の片
角に10〜20個程度（図示では３個のみを表示し、
他は昇略してある）据付けられる。損傷燃料保管
容器４は、損傷燃料保管容器貯蔵ラツク３の中に
設置される。 1 and 2 show the mounting position of the damaged fuel storage container storage rack 3 in the spent fuel pit 1. FIG. 1 is a partially omitted plan view, and FIG. The figure is a sectional view taken along the - line in FIG. 1. Most of the inside of the spent fuel pit 1 is occupied by spent fuel racks 2, and about 10 to 20 damaged fuel storage container storage racks 3 are located in one corner of the spent fuel pit 1 (3 in the figure). Show only the
(others are omitted) will be installed. The damaged fuel storage container 4 is installed in the damaged fuel storage container storage rack 3.
損傷燃料保管容器（以下単に容器という）４の
構造が第３図ないし第５図に示され、３図は平面
図、第４図は縦断面図、第５図は第４図の−
線に沿う横断面図である。容器４は、主に胴５、
底板２８、バスケツト２９、胴フランジ６及び蓋
７から成り、胴フランジ６は胴５に取付けられ
る。胴フランジ６の下側には、山形鋼８、補強材
９及びストッパ１０から成るバスケツト２９が取
付けられ、損傷燃料（図示せず。以下、燃料とい
う）は、バスケツト２９の中に収納される。バス
ケツト２９の長さは、燃料に組込まれている各種
の非核構成品と共に収納できる長さとされてい
る。 The structure of the damaged fuel storage container (hereinafter simply referred to as container) 4 is shown in FIGS. 3 to 5, where FIG. 3 is a plan view, FIG. 4 is a longitudinal sectional view, and FIG.
FIG. The container 4 mainly includes a body 5,
It consists of a bottom plate 28, a basket 29, a body flange 6 and a lid 7, and the body flange 6 is attached to the body 5. A basket 29 consisting of an angle iron 8, a reinforcing member 9 and a stopper 10 is attached to the lower side of the body flange 6, and damaged fuel (not shown, hereinafter referred to as fuel) is stored in the basket 29. The length of the basket 29 is such that it can be accommodated together with various non-nuclear components incorporated into the fuel.
容器４を水中に吊り下ろしたり、水中から容器
４を吊り上げるために、胴フランジ６に吊りピン
３０が取付けられている。容器４の吊り上げまた
は吊り下げは第６図に示すように、先端に吊り具
４６が取り付けられたワイヤロープ３１を使用済
燃料ピツトクレーンあるいは燃料取扱棟クレーン
のフツク３２に引掛けて行われる。あるいは第７
図に示すように、吊りワイヤロープ３３の先端を
吊りピン３０に固縛し、この吊りワイヤロープ３
３をクレーンフツク３２に引掛けて容器４を吊り
上げてもよい。但し、吊りワイヤロープ３３で吊
り上げまたは吊り下げる場合には、予じめ吊りワ
イヤロープ３３を容器４の吊りピン３０に固縛し
ておき、容器４を損傷燃料保管容器貯蔵ラツク３
に収納したあとも引続いて吊りワイヤロープ３３
を吊りピン３０に取付けたままにしておかなけれ
ばならない。そうしないと容器４を再び吊り上げ
ることができなくなる。なぜならば、使用済燃料
ピツト１内には高放射線を放出する使用済燃料が
沢山貯蔵されていることと、この放射線を遮蔽す
るために水が張られてあるが、この水が放射性物
質を多量に含んでいることから、ピツト１内に作
業員が立入ることができず、吊りピン３０への吊
りワイヤロープ３３の着脱ができないためであ
る。 A hanging pin 30 is attached to the body flange 6 in order to suspend the container 4 into the water or lift the container 4 out of the water. As shown in FIG. 6, the container 4 is lifted or suspended by hooking a wire rope 31 with a lifting device 46 attached to the tip to a hook 32 of a spent fuel pit crane or a fuel handling building crane. Or the seventh
As shown in the figure, the tip of the hanging wire rope 33 is secured to the hanging pin 30, and the hanging wire rope 3
3 may be hung on the crane hook 32 to lift the container 4. However, when lifting or suspending the container 4 using the hanging wire rope 33, the hanging wire rope 33 should be tied to the hanging pin 30 of the container 4 in advance, and the container 4 should be secured to the damaged fuel storage container storage rack 3.
The hanging wire rope 33 continues even after being stored in the
must remain attached to the hanging pin 30. Otherwise, the container 4 will not be able to be lifted again. This is because a large amount of spent fuel that emits high radiation is stored in spent fuel pit 1, and water is filled to shield this radiation, but this water contains a large amount of radioactive materials. This is because workers cannot enter the pit 1 and cannot attach or detach the hanging wire rope 33 to the hanging pin 30.
吊りワイヤロープ３３を常に容器４に取付けて
おく場合には、吊りワイヤロープ３３が使用済燃
料ピツト１内に落ちないようにするために、第８
図に示すように操作床面３５に取付られる係留用
金具３４あるいは第９図に示すように使用済燃料
ピツト１の周囲の手摺４０に固縛しておく。 When the hanging wire rope 33 is always attached to the container 4, in order to prevent the hanging wire rope 33 from falling into the spent fuel pit 1,
It is secured to a mooring metal fitting 34 attached to an operation floor 35 as shown in the figure or to a handrail 40 around the spent fuel pit 1 as shown in FIG.
蓋７は、損傷燃料を容器４のバスケツト２９に
出し入れする際に取外す必要があるが、この蓋７
は、別に準備される燃料取扱工具で吊れるよう
に、トツプノズル１１が蓋７に取付けられ、ま
た、操作床面３５上で、燃料取扱工具を用いるこ
となく蓋７が吊れるように、吊り金具１２が取り
付けられている。蓋７と胴フランジ６との密閉は
オーリング５３により行う。胴フランジ６には、
その中心を通る直線上に２本のセンタガイドピン
１３が取り付けてあり、蓋７の穴にセンタガイド
ピン１３を通すことにより、胴フランジ６と蓋７
とを中心を合わして芯出しができる。 The lid 7 needs to be removed when taking damaged fuel into and out of the basket 29 of the container 4;
The top nozzle 11 is attached to the lid 7 so that it can be hung with a separately prepared fuel handling tool, and a hanging bracket is installed on the operation floor 35 so that the lid 7 can be hung without using a fuel handling tool. 12 is attached. The lid 7 and the body flange 6 are sealed by an O-ring 53. The body flange 6 has
Two center guide pins 13 are attached on a straight line passing through the center, and by passing the center guide pins 13 through the holes in the lid 7, the body flange 6 and the lid 7
Centering can be done by aligning the and.
容器４内に収納された燃料がもし仮に異常に熱
を放出した場合、容器４内の水が膨脹して容器４
内に高い圧力が発生し、容器４自体が破損される
恐れがあるので、これを防ぐために、蓋７にレリ
ーフ弁１４が取り付けられている。このレリーフ
弁１４は逆止弁の機能も果すので容器４内の流体
を容器４外に放出する方向に取付ける。容器４内
の燃料の放出熱は、時間経過とともに、次第に弱
まり、いずれは熱を放出しなくなるが、もし仮に
レリーフ弁１４から異常膨脹した水が容器４外に
放出されたあとに容器４内の水が時間経過と共に
冷えてくると、水は元の容積に戻ろうとするの
で、容器４内には負圧が生じる。負圧が大きすぎ
れば、やはり容器４に損傷を与えるので、これを
避けるため、レリーフ弁１４′をレリーフ弁１４
とは逆の方向、すなわち容器４内にある程度以上
の負圧が立つた場合に容器４内に容器４外の水を
吸い込む方向に取付ける。 If the fuel stored in the container 4 abnormally releases heat, the water in the container 4 will expand and
In order to prevent this, a relief valve 14 is attached to the lid 7 to prevent high pressure from being generated inside the container 4 and damaging the container 4 itself. Since this relief valve 14 also functions as a check valve, it is installed in a direction that releases the fluid inside the container 4 to the outside of the container 4. The heat emitted from the fuel in the container 4 gradually weakens over time and eventually stops emitting heat. However, if abnormally expanded water is released from the relief valve 14 to the outside of the container 4, As the water cools down over time, it attempts to return to its original volume, creating negative pressure within the container 4. If the negative pressure is too large, it will still damage the container 4, so to avoid this, the relief valve 14' is
It is installed in the opposite direction, that is, in the direction in which water from outside the container 4 is sucked into the container 4 when a certain level of negative pressure is built up inside the container 4.
また、蓋７には、容器４の中の放射性物質の分
析あるいは監視用の試料水採取パイプを接続する
ためのクイツク継手１５が２個取付けられ、その
一方から容器４内の上部へ送水し、他方から胴フ
ランジ６に取付けられた内挿管１６を経て、容器
４内底部の水を取出せるようになつている。ある
いは内挿管１６を経て容器４内底部に送水し、容
器４内上方の水を取出すこともできる。 In addition, two quick fittings 15 are attached to the lid 7 to connect sample water collection pipes for analysis or monitoring of radioactive substances in the container 4, and one of the quick fittings 15 supplies water to the upper part of the container 4. Water from the inner bottom of the container 4 can be taken out from the other side through an inner tube 16 attached to the body flange 6. Alternatively, water can be supplied to the bottom of the container 4 through the inner tube 16 and the water above the container 4 can be taken out.
また、第１０図に示すように、このクイツク継
手１５に冷却水配管３６を接続して、この配管３
６にポンプ３７及び熱交換器３８を継いだうえで
閉ループを作り、これを利用して容器４内に冷た
い水を送り込んで、燃料の強制冷却を行うことも
できる。 In addition, as shown in FIG. 10, a cooling water pipe 36 is connected to this quick joint 15, and this pipe 3
6 is connected to a pump 37 and a heat exchanger 38 to create a closed loop, and this can be used to send cold water into the container 4 for forced cooling of the fuel.
蓋７を胴フランジ６に締付けるためのヒンジボ
ルト１７（第２図では10本具えている）が胴５に
固定された取付金具１８にピン１９で回転可能に
取付けられている。ヒンジボルト１７の詳細が第
１１図および第１２図に示され、ヒンジボルト１
７はばね２１で外方に倒され、その下端が取付金
具１８に当つて止まつた状態にある。蓋７を胴フ
ランジ６に近付け、蓋７に取付けた押し棒２２を
胴フランジ６の穴２３に挿入し、更に降すと、押
し棒２２の先端がヒンジボルト１７のＢ面を押す
ので、ヒンジボルト１７は立上り、胴フランジ６
及び蓋７の縁の切込み４１，４２の中へ入り込ん
で直立する。そこで第１３図および第１４図に示
すように使用済燃料ピツトクレーン２７の操作床
面から長いナツト取扱工具２５をピツト１内の水
中へ差入れてナツト２０を締める。ナツト２０は
ナツト取扱工具２５が嵌り易いように上方が先細
のテーパ付にしてある。蓋７を取除くときはナツ
ト取扱工具２５でナツト２０を弛め、蓋７を引上
げることによりピン２２の先端がＢ面から外れて
ヒンジボルト１７がばね２１の力で外方へ倒され
る。なお、ヒンジボルト１７が外方に倒れる際、
これが蓋７に引掛らないところまでナツト２０を
上げておくためにヒンジボルト１７の上端にスト
ツパ２４が設けられている。このようなヒンジボ
ルト１７を使うことにより、ナツト２０をボルト
１７から抜取らないので蓋７の取外し、取付がで
きるので作業が能率的に行われる。第１５図およ
び第１６図に、ナツト取扱工具２５の構造が示さ
れ、蓋７は、操作床面３５から凡そ８メートルほ
ど下にあるので、容器４のナツト２０を取扱うナ
ツト取扱工具２５も必然的に長尺のものにしなけ
ればならない。棒３９は鋼管或いは丸棒から作
り、その下端に六角穴（ナツトが六角ナツトの場
合）を有するスパナ４７を取付け、上端にはハン
ドル４８及びナツト取扱工具２５をクレーン等で
吊り上げる為のアイフツク４９が取付けられる。
ナツト取扱工具２５は、アイフツク４９により使
用済燃料ピツトクレーン２７のフツク３２に吊ら
れた状態でスパナ４７が容器４のナツト２０に嵌
合するように吊り下ろされる。ナツト取扱工具２
５は長尺であるが故に重く、使用済燃料ピツトク
レーン２７で吊つたままの状態でないと取扱い難
い。従つてアイフツク４９は、ナツト２０を締め
付けたり、緩めたりする際に、クレーンワイヤロ
ープ３１が捩れることのないように、棒３９に対
して空まわりするようにしてある。即ち、アイフ
ツク４９は、アイスリーブ５０及びアイナツト５
１により棒３９の上端金具５２に取付けられる。
アイフツク４９にアイスリーブ５０を通した状態
でアイナツト５１を軽く締込んで固定し、アイス
リーブ５０を金具５２の上端に固定する。これに
より、アイフツク４９を回転させることなく、即
ち、クレーンワイヤロープ３１を捩ることなく、
ナツト取扱工具２５を回転させることができ、ナ
ツト２０を支障なく締め付けたり、弛めたりする
ことができる。 Hinge bolts 17 (10 in FIG. 2) for fastening the lid 7 to the body flange 6 are rotatably attached to a mounting bracket 18 fixed to the body 5 with pins 19. Details of the hinge bolt 17 are shown in FIGS. 11 and 12, and the hinge bolt 1
7 is tilted outward by a spring 21, and its lower end hits the mounting bracket 18 and is in a stopped state. When the lid 7 is brought close to the body flange 6, the push rod 22 attached to the lid 7 is inserted into the hole 23 of the body flange 6, and then lowered further, the tip of the push rod 22 presses the B side of the hinge bolt 17, so the hinge The bolt 17 rises and the body flange 6
Then, it enters into the notches 41 and 42 on the edge of the lid 7 and stands upright. Therefore, as shown in FIGS. 13 and 14, a long nut handling tool 25 is inserted into the water in the pit 1 from the operation floor of the spent fuel pit crane 27 and the nut 20 is tightened. The nut 20 is tapered at the top so that a nut handling tool 25 can be easily fitted into the nut 20. When removing the lid 7, the nut 20 is loosened using a nut handling tool 25, and the lid 7 is pulled up so that the tip of the pin 22 comes off the B surface and the hinge bolt 17 is pushed outward by the force of the spring 21. In addition, when the hinge bolt 17 falls outward,
A stopper 24 is provided at the upper end of the hinge bolt 17 in order to raise the nut 20 until it does not catch on the lid 7. By using such a hinge bolt 17, the nut 20 is not removed from the bolt 17, so the lid 7 can be removed and attached, so that work can be done efficiently. 15 and 16 show the structure of the nut handling tool 25, and since the lid 7 is located approximately 8 meters below the operating floor 35, the nut handling tool 25 that handles the nuts 20 in the container 4 is also necessary. It must be of a long length. The rod 39 is made of a steel tube or a round rod, and a spanner 47 having a hexagonal hole (if the nut is a hexagonal nut) is attached to the lower end thereof, and an eye hook 49 for lifting the handle 48 and the nut handling tool 25 with a crane or the like is attached to the upper end. Installed.
The nut handling tool 25 is suspended from the hook 32 of the spent fuel pit crane 27 by an eye hook 49 so that the spanner 47 fits into the nut 20 of the container 4. Nut handling tool 2
5 is long and therefore heavy, and is difficult to handle unless it is suspended by the spent fuel pit crane 27. Therefore, the eye hook 49 is designed to freely rotate with respect to the rod 39 so that the crane wire rope 31 will not be twisted when the nut 20 is tightened or loosened. That is, the eye hook 49 is connected to the eye sleeve 50 and the eye nut 5.
1 is attached to the upper end fitting 52 of the rod 39.
With the eye sleeve 50 passed through the eye hook 49, the eye nut 51 is lightly tightened and fixed, and the eye sleeve 50 is fixed to the upper end of the metal fitting 52. As a result, without rotating the eye hook 49, that is, without twisting the crane wire rope 31,
The nut handling tool 25 can be rotated, and the nut 20 can be tightened or loosened without any trouble.
考案の効果
本考案による核燃料保管容器は、使用済燃料ピ
ツト内に保管され核燃料を水と共に内部に収容す
る胴と、上記核燃料を上記胴内に出し入れするた
めの開口を開閉する蓋と、上記胴内の圧力が所定
値以上に達したときに開弁して胴内の流体を外部
に流すレリーフ弁と、上記胴内の圧力が所定値以
下に達したときに開弁して外部の流体を胴内に導
入するレリーフ弁と、試料水採取パイプを接続す
るためのクイツク継手と、該クイツク継手と上記
胴内の下部を挿通する内挿管とを具えたことによ
り、次の効果を有する。Effects of the invention The nuclear fuel storage container according to the invention includes a shell that is stored in a spent fuel pit and contains nuclear fuel together with water, a lid that opens and closes an opening for taking the nuclear fuel into and out of the shell, and a lid that opens and closes an opening for taking the nuclear fuel in and out of the shell. A relief valve opens when the pressure inside the cylinder reaches a predetermined value or more and allows the fluid inside the cylinder to flow to the outside, and a relief valve opens when the pressure inside the cylinder reaches a predetermined value or less and allows the outside fluid to flow. By providing a relief valve introduced into the body, a quick joint for connecting a sample water collection pipe, and an inner tube inserted through the quick joint and the lower part of the body, the following effects are achieved.
核燃料を収容する胴は蓋によつて密閉すること
ができるので、この内部に収容される核燃料の被
覆管にピンホール等の欠陥があつても、放射性物
質が容器外に漏れることはないから、この容器を
使用済燃料ピツト内に長期間貯蔵しても、ピツト
内の水が放射性物質により汚染されることなく、
従つて、作業員の被曝線量増加の危険がなくな
る。そして、この容器内に収容された核燃料が多
量の熱を放出して容器内の圧力が異常に上昇した
場合には、レリーフ弁が開弁して容器内の流体を
外部に流出させることができ、また、容器内の流
体が冷却されることにより容器内の圧力が異常に
低下した場合には他のレリーフ弁が開弁して外部
の流体を容器内に導入できるので、容器を蓋によ
り密閉しても、容器がその内外の圧力差によつて
破損するのを防止できる。 The shell housing the nuclear fuel can be sealed with a lid, so even if there is a defect such as a pinhole in the nuclear fuel cladding tube housed inside, radioactive materials will not leak out of the container. Even if this container is stored in a spent fuel pit for a long time, the water in the pit will not be contaminated with radioactive materials.
Therefore, there is no risk of increased radiation exposure for workers. If the nuclear fuel stored in this container releases a large amount of heat and the pressure inside the container rises abnormally, the relief valve opens and the fluid inside the container can flow out. In addition, if the pressure inside the container drops abnormally due to the fluid inside the container being cooled, other relief valves open to allow outside fluid to enter the container, so the container can be sealed with a lid. This prevents the container from being damaged due to pressure differences between the inside and outside of the container.
更に、クイツク継手に試料水採取パイプを接続
することにより、これに連絡した内挿管を介し
て、密閉された容器内の底部から試料水を採取す
ることができる。また、クイツク継手に冷却水配
管を接続することにより、密閉された容器内に冷
却水を循環させて容器内の核燃料を強制冷却する
こともできる。 Furthermore, by connecting a sample water sampling pipe to the quick fitting, sample water can be sampled from the bottom of the sealed container via an internal tube connected to the pipe. Furthermore, by connecting a cooling water pipe to the quick joint, cooling water can be circulated within the sealed container to forcibly cool the nuclear fuel within the container.
図面は本考案の１実施例を示し、第１図は使用
済燃料ピツトを部分的に省略して示す平面図、第
２図は第１図の−線に沿う断面図、第３図は
核燃料保管容器の平面図、第４図は縦断面図、第
５図は第４図の−線に沿う断面図、第６図は
容器の吊り上げ要領の１例を示す正面図、第７図
は容器の他の吊り上げ要領を示す正面図、第８図
は吊りワイヤロープの係止要領の１例を示す正面
図、第９図は吊りワイヤロープの他の係止要領を
示す正面図、第１０図は容器内の冷却要領を示す
略示的回路図、第１１図は蓋の締結機構の詳細を
示す正面図、第１２図は同上の側面図、第１３図
は締結要領を示す正面図、第１４図は第１３図の
部拡大図、第１５図はナツト取扱工具を部分
的に破断し、かつ省略して示す正面図、第１６図
は第１５図の部分拡大図である。
使用済燃料ピツト……１、胴……５、蓋……
７、レリーフ弁……１４，１４′、クイツク継手
……１５、内挿管……１６。
The drawings show one embodiment of the present invention, in which Fig. 1 is a plan view with the spent fuel pit partially omitted, Fig. 2 is a sectional view taken along the - line in Fig. 1, and Fig. 3 is a nuclear fuel pit. A plan view of the storage container, FIG. 4 is a vertical sectional view, FIG. 5 is a sectional view taken along the - line in FIG. 4, FIG. 6 is a front view showing an example of how to lift the container, and FIG. FIG. 8 is a front view showing an example of a method for locking a hanging wire rope, FIG. 9 is a front view showing another method for locking a hanging wire rope, and FIG. 11 is a front view showing details of the lid fastening mechanism, FIG. 12 is a side view of the same, and FIG. 13 is a front view showing the fastening procedure. 14 is an enlarged view of a portion of FIG. 13, FIG. 15 is a front view of the nut handling tool partially cut away and omitted, and FIG. 16 is an enlarged view of a portion of FIG. 15. Spent fuel pit...1, shell...5, lid...
7. Relief valve...14, 14', Quick fitting...15, Internal tube...16.
Claims (1)
に内部に収容する胴と、上記核燃料を上記胴内に
出し入れするための開口を開閉する蓋と、上記胴
内の圧力が所定値以上に達したときに開弁して胴
内の流体を外部に流すレリーフ弁と、上記胴内の
圧力が所定値以下に達したときに開弁して外部の
流体を胴内に導入するレリーフ弁と、試料水採取
パイプを接続するためのクイツク継手と、該クイ
ツク継手と上記胴内の下部を挿通する内挿管とを
具えたことを特徴とする核燃料保管容器。 A shell that is stored in a spent fuel pit and contains nuclear fuel together with water, a lid that opens and closes an opening for taking the nuclear fuel in and out of the shell, and when the pressure inside the shell reaches a predetermined value or more. a relief valve that opens when the pressure inside the cylinder reaches a predetermined value or less to allow the fluid inside the cylinder to flow outside; a relief valve that opens when the pressure inside the cylinder reaches a predetermined value or less and introduces external fluid into the cylinder; 1. A nuclear fuel storage container comprising: a quick fitting for connecting a sampling pipe; and an inner tube inserted through the quick fitting and the lower part of the barrel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1983144465U JPS6053093U (en) | 1983-09-20 | 1983-09-20 | nuclear fuel storage container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1983144465U JPS6053093U (en) | 1983-09-20 | 1983-09-20 | nuclear fuel storage container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6053093U JPS6053093U (en) | 1985-04-13 |
| JPH0216318Y2 true JPH0216318Y2 (en) | 1990-05-02 |
Family
ID=30322149
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1983144465U Granted JPS6053093U (en) | 1983-09-20 | 1983-09-20 | nuclear fuel storage container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6053093U (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5638201B2 (en) * | 2009-03-19 | 2014-12-10 | 三菱重工業株式会社 | Basket and cask |
| JP2014529737A (en) * | 2011-08-19 | 2014-11-13 | ホルテック・インターナショナル・インコーポレーテッド | Container and system for handling damaged nuclear fuel and method of manufacturing the same |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5489197A (en) * | 1977-12-16 | 1979-07-14 | Nl Industries Inc | Confining of radioactive substances under dried condition |
| JPS5557192A (en) * | 1978-10-25 | 1980-04-26 | Mitsubishi Heavy Ind Ltd | Cask for spent fuel assembly |
-
1983
- 1983-09-20 JP JP1983144465U patent/JPS6053093U/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5489197A (en) * | 1977-12-16 | 1979-07-14 | Nl Industries Inc | Confining of radioactive substances under dried condition |
| JPS5557192A (en) * | 1978-10-25 | 1980-04-26 | Mitsubishi Heavy Ind Ltd | Cask for spent fuel assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6053093U (en) | 1985-04-13 |
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