JP4276828B2 - Radioactive material dry storage building - Google Patents

Radioactive material dry storage building Download PDF

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Publication number
JP4276828B2
JP4276828B2 JP2002315222A JP2002315222A JP4276828B2 JP 4276828 B2 JP4276828 B2 JP 4276828B2 JP 2002315222 A JP2002315222 A JP 2002315222A JP 2002315222 A JP2002315222 A JP 2002315222A JP 4276828 B2 JP4276828 B2 JP 4276828B2
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radioactive material
fuel
storage
radioactive
air
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JP2004150906A (en
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寿治 斉藤
雅彦 田辺
仁 清水
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Hitachi GE Nuclear Energy Ltd
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Hitachi GE Nuclear Energy Ltd
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Cooling, Air Intake And Gas Exhaust, And Fuel Tank Arrangements In Propulsion Units (AREA)

Description

【0001】
【発明の属する技術分野】
本発明は、放射性物質乾式貯蔵建屋に係り、特に、原子力発電所から発生する使用済燃料集合体、及び高レベル放射性廃棄物のガラス固化体等の放射性物質を貯蔵するのに好適な放射性物質乾式貯蔵建屋に関する。
【0002】
【従来の技術】
原子力発電所から発生する使用済燃料燃料集合体は、ウラン及びプルトニウム等の再使用可能な核燃料物質を回収するために再処理される。発生した高レベル放射性廃棄物はガラス固化される。このガラス固化体は、崩壊熱による発熱量が小さくなって処分が可能になるまでの間、冷却しながら貯蔵する必要がある。また、使用済燃料集合体は、再処理されるまでの間、原子力発電所内の貯蔵プールに保管される。しかし、年々増大する使用済燃料集合体に原子力発電所内の貯蔵プールが容量不足となり、使用済燃料集合体を一時的に貯蔵できる新たな貯蔵建屋の建設が望まれている。
【0003】
これらの目的に対応した放射性物質乾式貯蔵建屋の一例が、例えば特許文献1に開示されている。この放射性物質乾式貯蔵建屋は、使用済燃料集合体を貯蔵する複数の燃料貯蔵室を有する。各燃料貯蔵室は、仕切り壁で仕切られている。各燃料貯蔵室は、使用済燃料集合体を収納した複数の収納管が配置される。外気取入口から流入した空気は、燃料貯蔵室内に流入して収納管を冷却して排気口から外部に排出される。燃料貯蔵室内の収納管への使用済燃料集合体の収納作業は、燃料貯蔵室上方に位置する燃料装荷室内を移動する、自走式装荷機である床面走行クレーンにより行われる。使用済燃料集合体は、キャニスタに装荷された状態で収納管内に収納される。
【0004】
【特許文献1】
特開平2000−193786号公報,5〜7頁,図1〜図4
【0005】
【発明が解決しようとする課題】
大規模な床面走行クレーンは全燃料貯蔵室の上方を走行するため、燃料装荷室内には床面走行クレーンの移動を妨げる壁,柱等の建築構造上の構造部材を設置することができない。従って、燃料装荷室の天井、すなわち放射性物質乾式貯蔵建屋の屋根は、その荷重を支えるため、大規模な鉄骨構造あるいはトラス構造にする必要があった。また、床面走行クレーンの走行に必要となる燃料装荷室内の有効スペースは、この大規模な鉄骨構造あるいは、トラス構造部材の下端より下方となる。大規模な鉄骨構造あるいはトラス構造のふところ部はデッドスペースとなり、放射性物質乾式貯蔵建屋は建屋容積が増加する。更に、燃料貯蔵室の空気流れ方向におけるスパンの寸法は、床面走行クレーンの桁寸法と相関がある。すなわち、燃料貯蔵室の空気流れ方向のスパン寸法を大きくすると、床面走行クレーンの桁寸法も大きくなり、床面走行クレーン荷重が必要以上に大きくなる。このため、燃料貯蔵室の空気流れ方向の長さを大きくできない。
【0006】
本発明の目的は、屋根の構造を簡素化できる放射性物質乾式貯蔵建屋を提供することにある。
【0007】
【課題を解決するための手段】
上記した目的を達成する本発明の特徴は、互いに側壁で分離され、放射性物質を収納する複数の収納管が配置される放射性物質貯蔵室の上方に形成された放射性物質装荷領域の床面上に、放射性物質搬送手段が通過できるように、屋根を支持する壁及び柱の一方を設置したことにある。その放射性物質装荷領域を覆う屋根の重量がその壁または柱で支持されるため、屋根の構造を簡素化できる。
【0008】
好ましくは、その壁または柱が、隣接する放射性物質貯蔵室相互間に形成される側壁の延長線上に配置されている。このため、その壁または柱で支持している屋根の荷重をその側壁に直接伝えることができ、放射性物質貯蔵室の天井、すなわち放射性物質装荷領域の床の厚みを薄くてすむ。
【0009】
【発明の実施の形態】
本発明の好適な放射性物質乾式貯蔵建屋の実施例を、図1〜図4を用いて以下に説明する。
【0010】
本実施例の放射性物質乾式貯蔵建屋1は、複数の燃料貯蔵室(放射性物質貯蔵室)2及び複数の燃料装荷室(放射性物質装荷領域)13を有する。鉄筋コンクリート製の放射性物質乾式貯蔵建屋1は、3つの燃料貯蔵室2と3つの燃料装荷室13を有する。各燃料貯蔵室2は、天井スラブ3と床スラブ4との間に形成される。複数の収納管5が各燃料貯蔵室2内に配置される。これらの収納管5は、上端部が天井スラブ3に取り付けられ、垂直方向において床スラブ4に向かって伸びている。各収納管5は、上端部に着脱可能に遮蔽プラグ18が取り付けられている。遮蔽プラグ18を収納管5から取り外したとき、収納管5内の空間は、燃料装荷室13と連通される。各燃料貯蔵室2は、高さ方向の中間に仕切部材10を水平方向に設置している。各収納管5は仕切部材10を貫通している。各燃料貯蔵室2は、仕切部材10と天井スラブ3との間に上部冷却流路28を、仕切部材10と床スラブ4との間に下部冷却流路29をそれぞれ形成している。燃料貯蔵室2、具体的には上部冷却流路28及び下部冷却流路29が空気流入通路6に連絡される。空気流入通路6は空気取入口17を介して放射性物質乾式貯蔵建屋1の外部とつながっている。燃料貯蔵室2、具体的には上部冷却流路28及び下部冷却流路29は、空気排出通路7に連絡される。空気排出通路7は空気吐出口17を介して外部とつながっている。隣り合うそれぞれの燃料貯蔵室2は、側壁21によって互いに分離されている。整流部材8Aが空気流入通路6側で仕切部材10上に設置される。整流部材8Bが空気流入通路6側で床スラブ4上に設置される。整流部材9Aが空気排出通路7側で仕切部材10上に設置される。整流部材9Bが空気排出通路7側で床スラブ4上に設置される。
【0011】
棒状放射線遮蔽体42は、収納管5の群よりも上流側の上部冷却流路28内に、収納管5の群よりも下流側の下部冷却流路29内に、収納管5の群よりも上流側の上部冷却流路28内に、収納管5の群よりも下流側の下部冷却流路29内に、それぞれ水平方向に伸びて配置される。それらの棒状放射線遮蔽体42の設置位置において、上流側に位置する棒状放射線遮蔽体42は、高さ方向において、下流側に位置する棒状放射線遮蔽体42相互間に形成される間隙に面するように配置される。このような配置によって、収納管5内の使用済燃料集合体から放出される放射線がそれらの棒状放射線遮蔽体42によって遮蔽される。
【0012】
各燃料装荷室13は、各燃料貯蔵室2の上方に位置しており、天井スラブ3の上方に位置している。隣接するそれぞれの燃料装荷室13の相互間には、側壁20が設けられる。側壁20は側壁21の延長線上で天井スラブ3上に設置される。それぞれの側壁20は、放射性物質乾式貯蔵建屋1の屋根30を支えている。キャニスタを搬送するエアパレット式搬送車16が通過できる開口部23が、各側壁20に形成される。開口部23はエアパレット式搬送車16が通る通路である。このため、各燃料装荷室13は、開口部23により連絡されている。
【0013】
搬送車であるエアパレット式搬送車16は、エアパレット24を下部に設けた車台43、及び巻上装置26を上部に設置したキャニスタ収納ケーシング44を備える。エアパレット式搬送車16は、使用済燃料集合体を内蔵したキャニスタをキャニスタ収納ケーシング44内で車台43上に載せて搬送することができる。エアパレット式搬送車16は、燃料装荷室13内で燃料装荷室13の床面(天井スラブ3の上面)上を移動する。エアパレット式搬送車16は、エアパレット24から下向きに空気を噴出して浮上させ、図示されていない走行用動力部(例えば、特開2002−148386号公報に記載された台車)により前進または後進される。
【0014】
原子力発電所内において、使用済燃料集合体はキャニスタ34内に収納され、更にキャニスタ34が燃料輸送容器32内に収納される。燃料輸送容器32はトレーラ31にて原子力発電所から放射性物質乾式貯蔵建屋1まで搬送される。燃料輸送容器32は、放射性物質乾式貯蔵建屋1内で、天井クレーン36(図4参照)を用いてトレーラ31から吊り上げられ、開口部であるハッチ25,キャニスタハンドリングエリア37及び開口部であるハッチ38を介してキャニスタ受入室35に移される。キャニスタハンドリングエリア37は、キャニスタ受入室35及び燃料輸送容器保管室33の上方に形成される。キャニスタ受入室35内で燃料輸送容器32の蓋がはずされて、燃料輸送容器32内のキャニスタ34が、キャニスタ受入室35内の天井クレーン39(図4参照)にて吊り上げられ、燃料輸送容器32から取り出される。キャニスタ34が取り出された燃料輸送容器32は、天井クレーン36にて、ハッチ38,キャニスタハンドリングエリア37及び開口部27を介して燃料輸送容器保管室33に運ばれ、ここに一時保管される。キャニスタ34は、天井クレーン36によりハッチ38を通して上方のキャニスタハンドリングエリア37まで吊り上げられる。キャニスタ34は、キャニスタハンドリングエリア37内でエアパレット式搬送車16に載置される。具体的には、そのキャニスタ34はキャニスタ収納ケーシング44内で車台43上に載置される。ハッチ25,38及び開口部27は、キャニスタハンドリングエリア37の床(キャニスタ受入室35の天井)に形成される。ハッチ25,38は燃料輸送容器32またはキャニスタ34を通す以外は、グレーチングで覆われている。
【0015】
エアパレット式搬送車16は、駆動されて、キャニスタハンドリングエリア37とこれに隣接する燃料装荷室13とを仕切っている側壁40に設けられた開口部41を通ってキャニスタハンドリングエリア37に隣接する燃料装荷室13内に達する。開口部41は、開閉できる扉によって封鎖される。エアパレット式搬送車16は、更に、キャニスタ34を装荷すべき収納管5が存在する燃料貯蔵室2の真上にある所定の燃料装荷室(例えば、図3において最も右側にある燃料装荷室)13まで移動する。この移動の際には、エアパレット式搬送車16は側壁20に形成された開口部23を通る。開口部23はエアパレット式搬送車16が通過できる大きさを有する。エアパレット式搬送車16が燃料装荷室13内で所定の収納管5の真上に到達したとき、巻上装置26により収納管5の上端部を封鎖している遮蔽プラグ18を吊り上げてエアパレット式搬送車16に収納する。次に、エアパレット式搬送車16に載置しているキャニスタ34は、巻上装置26で一旦吊り上げられ、その後、収納管5内に降ろされる。キャニスタ34を収納管5内に収納した後、エアパレット式搬送車16に収納された遮蔽プラグ18を巻上装置26により該当する収納管5の上端部に降ろし、その遮蔽プラグ18をその収納管5に取り付けて密封する。エアパレット式搬送車16は、決められた軌道上ではなく、燃料装荷室13等の床面上を自由に移動できる。
【0016】
放射性物質乾式貯蔵建屋1外の空気は空気取入口17から空気流入通路6内に流入する。この空気は、空気流入通路6、及び棒状放射線遮蔽体42の間をそれぞれ通って、燃料貯蔵室2内の上部冷却流路28及び下部冷却流路29内に達する。収納管5内のキャニスタ内に収納された使用済燃料集合体から放出される熱は、収納管5に伝えられる。それぞれの流路内で、収納管5の相互間を通過する空気は、収納管5の上記の熱を奪い、収納管5を冷却する。収納管5の相互間を通過した空気は、下流側に配置された棒状放射線遮蔽体42の相互間を通過して、空気排出通路7を通り、空気吐出口17より外部に排出される。
【0017】
本実施例は、燃料装荷室13間に設けられた側壁20が屋根30を支えているため、屋根30の荷重を、放射性物質乾式貯蔵建屋1の外面を形成する側壁(例えば、空気流入通路6及び空気排出通路7を形成するそれぞれの側壁)だけでなく、側壁20によって支えることができる。従って、屋根30の構造を簡素化できる。特に、屋根30自体に要求される強度を支持点の増加により低下できるので、屋根30の重量も低減できる。これも、屋根30の構造の簡素化に貢献する。従来例において屋根の強度増大のために高さ方向に幅のある構造材(例えば、トラス)を屋根に用いている関係上、屋根の下方にデッドスペースが形成され、屋根の上面のレベルが高くなっていた。本実施例では、屋根30が側壁20によって支持されるため、屋根30を構成する構造材の高さ方向の幅を狭くすることができる。このため、上記デッドスペースを低減でき、更には屋根30の上面のレベルを低減できる。
【0018】
側壁20が燃料貯蔵室2間に設けられた側壁21の延長線上に位置しているので、屋根30の荷重を側壁20から側壁21に伝えることができる。従って、天井スラブ3の厚みを増すことなく、屋根30の荷重を床スラブ4に伝えることができる。複数の側壁20が各側壁20に対応する側壁21の延長線上にそれぞれ配置されているため、屋根30の荷重を分散させて床スラブに伝えることができる。本実施例によれば、耐震性に優れた、合理的でかつスペース効率のよい放射性物質乾式貯蔵建屋を得ることができる。
【0019】
側壁20が、隣接する燃料貯蔵室2相互間に形成される側壁21の延長線上に配置されているため、その側壁20で支持している屋根30の荷重をその側壁20に直接伝えることができ、天井スラブ3、すなわち燃料装荷室13の床の厚みを厚くする必要がなく、その厚みが薄くてすむ。
【0020】
以上述べた本実施例の各効果は、床面上を自由に移動できるエアパレット式搬送車16を用いてキャニスタ34を搬送することによってもたらされたのである。
【0021】
開口部23を有する側壁20の水平方向における両端が、空気流入通路6を形成する側壁と空気排出通路7を形成する他の側壁に結合されているため、放射性物質乾式貯蔵建屋1の耐震性が更に向上する。
【0022】
更には、重量が重い従来の床面走行クレーンを用いずに重量の軽いエアパレット式搬送車16を用いるため、天井スラブ3に加わる荷重を低減できる。エアパレット式搬送車16の適用は、燃料貯蔵室2における冷却空気の流れ方向における放射性物質乾式貯蔵建屋の幅を自由に設定できるようになる。
【0023】
本実施例は、側壁20に支持される屋根30の躯体を厚くすることができるため、従来、燃料貯蔵室の天井スラブで行っていた外部飛来物に対する防護を、燃料装荷室13の天井、すなわち屋根30で行うことができる。このため、キャニスタを搬送する搬送設備、具体的にはエアパレット式搬送車16への外部飛来物に対する防護対策を行う必要がなくなる。
【0024】
上記した実施例は、側壁20に開口部23を形成しているが、側壁20に開口部23を形成しないで、側壁20で区切られた燃料装荷室(放射性物質装荷室)13間を移動できる、エアパレット式搬送車16の搬送車用通路を形成してもよい。すなわち、側壁20の一方の端面と空気流入通路6を形成する側壁との間(側壁20の他方の端面とまたは空気排出通路7を形成する他の側壁との間)に、搬送車用通路を形成する。前述した開口部23も搬送車用通路である。
【0025】
上記した実施例は、複数の燃料貯蔵室2の上方に側壁20で仕切られた複数の燃料装荷室13を形成しているが、複数の燃料貯蔵室2の上方に側壁20のない1つの広い燃料装荷室を形成してもよい。この場合、屋根30は、側壁20の替りに、側壁21の真上(側壁21の延長線上)に設置した複数の柱によって支持される。1つの側壁21の真上に設置された複数の柱間の間隔の少なくとも1つの間隔は、エアパレット式搬送車16がその間隔を形成する2つの柱間を通過できる幅となっていればよい。エアパレット式搬送車16が通過できる幅を有する2つの柱間に、搬送車用通路が形成されていると言える。
【0026】
また、放射性物質乾式貯蔵建屋1は、使用済燃料集合体を貯蔵することを例にとって説明したが、使用済燃料集合体の替りに高レベル放射性廃棄物のガラス固化体等の放射性廃棄物固化体を収納管5内に収納する場合にも適用できる。
【0027】
【発明の効果】
本発明によれば、燃料装荷室間に設けられた側壁が屋根を支えており、軽量のエアパレット式搬送車を用いるため、放射性物質乾式貯蔵建屋の屋根の構造を簡素化できる。
【図面の簡単な説明】
【図1】本発明の好適な一実施例である放射性物質乾式貯蔵建屋の縦断面図(図2及び図3のI−I断面図)である。
【図2】図1のII−II断面図である。
【図3】図1のIII−III断面図である。
【図4】図2及び図3のIV−IV断面図である。
【符号の説明】
1…放射性物質乾式貯蔵建屋、2…燃料貯蔵室、3…天井スラブ、4…床スラブ、5…収納管、6…空気流入通路、7…空気排出通路、10…仕切部材、13…燃料装荷室、16…エアパレット式搬送車、20,21…側壁、23…開口部、24…エアパレット、26…巻上げ装置、28…上部冷却流路、29…下部冷却流路、44…キャニスタ収納ケーシング。
[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a radioactive material dry storage building, and in particular, a radioactive material dry type suitable for storing radioactive materials such as spent fuel assemblies generated from nuclear power plants and vitrified bodies of high-level radioactive waste. Regarding storage building.
[0002]
[Prior art]
Spent fuel fuel assemblies originating from nuclear power plants are reprocessed to recover reusable nuclear fuel materials such as uranium and plutonium. The generated high-level radioactive waste is vitrified. This vitrified body needs to be stored while being cooled until the calorific value due to decay heat becomes small and disposal becomes possible. The spent fuel assembly is stored in a storage pool in the nuclear power plant until it is reprocessed. However, the capacity of the storage pool in the nuclear power plant becomes insufficient for the spent fuel assemblies that are increasing year by year, and it is desired to construct a new storage building that can temporarily store the spent fuel assemblies.
[0003]
An example of a radioactive substance dry storage building corresponding to these purposes is disclosed in Patent Document 1, for example. This radioactive material dry storage building has a plurality of fuel storage chambers for storing spent fuel assemblies. Each fuel storage chamber is partitioned by a partition wall. Each fuel storage chamber is provided with a plurality of storage pipes storing spent fuel assemblies. The air flowing in from the outside air inlet flows into the fuel storage chamber, cools the storage pipe, and is discharged outside through the exhaust port. The storage operation of the spent fuel assembly in the storage pipe in the fuel storage chamber is performed by a floor traveling crane that is a self-propelled loading machine that moves in the fuel loading chamber located above the fuel storage chamber. The spent fuel assembly is stored in the storage pipe while being loaded on the canister.
[0004]
[Patent Document 1]
Japanese Patent Laid-Open No. 2000-193786, pages 5 to 7, FIGS. 1 to 4
[0005]
[Problems to be solved by the invention]
Since a large-scale floor traveling crane travels above the entire fuel storage chamber, it is not possible to install structural members such as walls and pillars that hinder the movement of the floor traveling crane in the fuel loading chamber. Therefore, the ceiling of the fuel loading chamber, that is, the roof of the radioactive material dry storage building, has to have a large-scale steel structure or truss structure to support the load. Moreover, the effective space in the fuel loading chamber required for the traveling of the floor traveling crane is lower than the lower end of the large steel structure or truss structure member. The large steel structure or truss structure has a dead space, and the radioactive material dry storage building increases the building volume. Furthermore, the dimension of the span in the air flow direction of the fuel storage chamber correlates with the girder dimension of the floor traveling crane. That is, when the span dimension in the air flow direction of the fuel storage chamber is increased, the girder dimension of the floor traveling crane is also increased, and the floor traveling crane load is increased more than necessary. For this reason, the length of the fuel storage chamber in the air flow direction cannot be increased.
[0006]
An object of the present invention is to provide a radioactive material dry storage building capable of simplifying the structure of a roof.
[0007]
[Means for Solving the Problems]
A feature of the present invention that achieves the above-described object is that a radioactive material loading area formed above a radioactive material storage chamber, which is separated from each other by a side wall and is provided with a plurality of storage tubes for storing radioactive materials, is provided on the floor surface. One of the walls and pillars supporting the roof is installed so that the radioactive material transport means can pass therethrough. Since the weight of the roof covering the radioactive material loading area is supported by the wall or pillar, the structure of the roof can be simplified.
[0008]
Preferably, the wall or column is arranged on an extension of the side wall formed between adjacent radioactive substance storage chambers. For this reason, the load of the roof supported by the wall or pillar can be directly transmitted to the side wall, and the thickness of the ceiling of the radioactive material storage chamber, that is, the floor of the radioactive material loading area can be reduced.
[0009]
DETAILED DESCRIPTION OF THE INVENTION
An example of a preferred radioactive material dry storage building of the present invention will be described below with reference to FIGS.
[0010]
The radioactive substance dry storage building 1 of the present embodiment has a plurality of fuel storage rooms (radioactive substance storage rooms) 2 and a plurality of fuel loading rooms (radioactive substance loading areas) 13. The radioactive material dry storage building 1 made of reinforced concrete has three fuel storage chambers 2 and three fuel loading chambers 13. Each fuel storage chamber 2 is formed between the ceiling slab 3 and the floor slab 4. A plurality of storage tubes 5 are arranged in each fuel storage chamber 2. The upper ends of these storage pipes 5 are attached to the ceiling slab 3 and extend toward the floor slab 4 in the vertical direction. Each storage tube 5 has a shielding plug 18 attached to the upper end portion in a removable manner. When the shielding plug 18 is removed from the storage tube 5, the space in the storage tube 5 is communicated with the fuel loading chamber 13. Each fuel storage chamber 2 is provided with a partition member 10 in the horizontal direction in the middle of the height direction. Each storage tube 5 penetrates the partition member 10. Each fuel storage chamber 2 forms an upper cooling flow path 28 between the partition member 10 and the ceiling slab 3, and a lower cooling flow path 29 between the partition member 10 and the floor slab 4. The fuel storage chamber 2, specifically, the upper cooling passage 28 and the lower cooling passage 29 are connected to the air inflow passage 6. The air inflow passage 6 is connected to the outside of the radioactive substance dry storage building 1 through an air intake port 17. The fuel storage chamber 2, specifically, the upper cooling passage 28 and the lower cooling passage 29 are connected to the air discharge passage 7. The air discharge passage 7 is connected to the outside through an air discharge port 17. Adjacent fuel storage chambers 2 are separated from each other by side walls 21. The rectifying member 8A is installed on the partition member 10 on the air inflow passage 6 side. The rectifying member 8B is installed on the floor slab 4 on the air inflow passage 6 side. The rectifying member 9A is installed on the partition member 10 on the air discharge passage 7 side. The flow regulating member 9B is installed on the floor slab 4 on the air discharge passage 7 side.
[0011]
The rod-shaped radiation shield 42 is located in the upper cooling flow path 28 on the upstream side of the group of the storage tubes 5 and in the lower cooling flow path 29 on the downstream side of the storage tube 5 group. In the upper cooling flow path 28 on the upstream side, the lower cooling flow paths 29 on the downstream side of the group of the storage pipes 5 are respectively extended in the horizontal direction. At the installation position of the rod-shaped radiation shields 42, the rod-shaped radiation shields 42 located on the upstream side face the gap formed between the rod-shaped radiation shields 42 located on the downstream side in the height direction. Placed in. With this arrangement, the radiation emitted from the spent fuel assembly in the storage tube 5 is shielded by the rod-shaped radiation shields 42.
[0012]
Each fuel loading chamber 13 is located above each fuel storage chamber 2 and above the ceiling slab 3. Side walls 20 are provided between the adjacent fuel loading chambers 13. The side wall 20 is installed on the ceiling slab 3 on the extended line of the side wall 21. Each side wall 20 supports the roof 30 of the radioactive substance dry storage building 1. An opening 23 through which the air pallet type transport vehicle 16 that transports the canister can pass is formed in each side wall 20. The opening 23 is a passage through which the air pallet type transport vehicle 16 passes. For this reason, each fuel loading chamber 13 is in communication with the opening 23.
[0013]
The air pallet type transport vehicle 16 that is a transport vehicle includes a chassis 43 provided with an air pallet 24 at a lower portion and a canister storage casing 44 provided with a hoisting device 26 at an upper portion. The air pallet type transport vehicle 16 can transport a canister with a built-in spent fuel assembly mounted on a chassis 43 in a canister storage casing 44. The air pallet type transport vehicle 16 moves on the floor surface of the fuel loading chamber 13 (the upper surface of the ceiling slab 3) in the fuel loading chamber 13. The air pallet type transport vehicle 16 blows air downward from the air pallet 24 and floats, and moves forward or backward by a traveling power unit (not shown) (for example, a carriage described in JP-A-2002-148386). Is done.
[0014]
In the nuclear power plant, the spent fuel assembly is stored in the canister 34, and the canister 34 is further stored in the fuel transport container 32. The fuel transport container 32 is transported from the nuclear power plant to the radioactive material dry storage building 1 by the trailer 31. The fuel transport container 32 is lifted from the trailer 31 by using an overhead crane 36 (see FIG. 4) in the radioactive substance dry storage building 1, and is a hatch 25, a canister handling area 37, and a hatch 38 that is an opening. To the canister receiving chamber 35. The canister handling area 37 is formed above the canister receiving chamber 35 and the fuel transport container storage chamber 33. The lid of the fuel transport container 32 is removed in the canister receiving chamber 35, and the canister 34 in the fuel transport container 32 is lifted by an overhead crane 39 (see FIG. 4) in the canister receiving chamber 35. Taken from. The fuel transport container 32 from which the canister 34 has been taken out is transported to the fuel transport container storage chamber 33 by the overhead crane 36 through the hatch 38, the canister handling area 37, and the opening 27, and is temporarily stored therein. The canister 34 is lifted by the overhead crane 36 through the hatch 38 to the upper canister handling area 37. The canister 34 is placed on the air pallet transport vehicle 16 in the canister handling area 37. Specifically, the canister 34 is placed on the chassis 43 in the canister storage casing 44. The hatches 25 and 38 and the opening 27 are formed on the floor of the canister handling area 37 (the ceiling of the canister receiving chamber 35). The hatches 25 and 38 are covered with grating except for passing the fuel transport container 32 or the canister 34.
[0015]
The air pallet type transport vehicle 16 is driven, and the fuel adjacent to the canister handling area 37 passes through an opening 41 provided in the side wall 40 that partitions the canister handling area 37 and the fuel loading chamber 13 adjacent thereto. It reaches into the loading chamber 13. The opening 41 is sealed by a door that can be opened and closed. The air pallet-type transport vehicle 16 further has a predetermined fuel loading chamber (for example, the rightmost fuel loading chamber in FIG. 3) directly above the fuel storage chamber 2 where the storage pipe 5 in which the canister 34 is loaded. Move to 13. During this movement, the air pallet transport vehicle 16 passes through an opening 23 formed in the side wall 20. The opening 23 has a size through which the air pallet type transport vehicle 16 can pass. When the air pallet-type transport vehicle 16 reaches directly above the predetermined storage tube 5 in the fuel loading chamber 13, the hoisting device 26 lifts the shielding plug 18 that seals the upper end of the storage tube 5 to lift the air pallet. It is stored in the transport vehicle 16. Next, the canister 34 placed on the air pallet type transport vehicle 16 is once lifted by the hoisting device 26 and then lowered into the storage tube 5. After the canister 34 is stored in the storage tube 5, the shielding plug 18 stored in the air pallet type transport vehicle 16 is lowered to the upper end portion of the corresponding storage tube 5 by the hoisting device 26, and the shielding plug 18 is moved to the storage tube. Attach to 5 and seal. The air pallet-type transport vehicle 16 can freely move on the floor surface of the fuel loading chamber 13 and the like, not on a predetermined track.
[0016]
Air outside the radioactive substance dry storage building 1 flows into the air inflow passage 6 from the air intake port 17. This air passes through the air inflow passage 6 and the rod-shaped radiation shield 42, respectively, and reaches the upper cooling flow path 28 and the lower cooling flow path 29 in the fuel storage chamber 2. The heat released from the spent fuel assembly stored in the canister in the storage tube 5 is transmitted to the storage tube 5. In each flow path, the air passing between the storage tubes 5 takes the heat of the storage tubes 5 and cools the storage tubes 5. The air that has passed between the storage tubes 5 passes between the rod-shaped radiation shields 42 arranged on the downstream side, passes through the air discharge passage 7, and is discharged to the outside from the air discharge port 17.
[0017]
In the present embodiment, since the side walls 20 provided between the fuel loading chambers 13 support the roof 30, the load on the roof 30 is applied to the side walls (for example, the air inflow passage 6) that form the outer surface of the radioactive substance dry storage building 1. And the respective side walls forming the air discharge passage 7), as well as the side walls 20. Therefore, the structure of the roof 30 can be simplified. In particular, since the strength required for the roof 30 itself can be reduced by increasing the support points, the weight of the roof 30 can also be reduced. This also contributes to simplification of the structure of the roof 30. In the conventional example, in order to increase the strength of the roof, a structure material having a width in the height direction (for example, a truss) is used for the roof, so a dead space is formed below the roof, and the level of the upper surface of the roof is high. It was. In the present embodiment, since the roof 30 is supported by the side walls 20, the width in the height direction of the structural material constituting the roof 30 can be reduced. For this reason, the said dead space can be reduced and also the level of the upper surface of the roof 30 can be reduced.
[0018]
Since the side wall 20 is located on the extension line of the side wall 21 provided between the fuel storage chambers 2, the load of the roof 30 can be transmitted from the side wall 20 to the side wall 21. Therefore, the load of the roof 30 can be transmitted to the floor slab 4 without increasing the thickness of the ceiling slab 3. Since the plurality of side walls 20 are arranged on the extension lines of the side walls 21 corresponding to the respective side walls 20, the load of the roof 30 can be distributed and transmitted to the floor slab. According to the present embodiment, it is possible to obtain a rational and space-efficient radioactive material dry storage building excellent in earthquake resistance.
[0019]
Since the side wall 20 is disposed on an extension line of the side wall 21 formed between the adjacent fuel storage chambers 2, the load of the roof 30 supported by the side wall 20 can be directly transmitted to the side wall 20. It is not necessary to increase the thickness of the ceiling slab 3, that is, the floor of the fuel loading chamber 13, and the thickness can be reduced.
[0020]
Each effect of the present embodiment described above is brought about by transporting the canister 34 using the air pallet type transport vehicle 16 that can freely move on the floor surface.
[0021]
Since both ends in the horizontal direction of the side wall 20 having the opening 23 are connected to the side wall forming the air inflow passage 6 and the other side wall forming the air discharge passage 7, the seismic resistance of the radioactive substance dry storage building 1 is improved. Further improvement.
[0022]
Furthermore, since the light weight air pallet type conveyance vehicle 16 is used without using a heavy conventional floor traveling crane, the load applied to the ceiling slab 3 can be reduced. The application of the air pallet transport vehicle 16 allows the width of the radioactive substance dry storage building in the flow direction of the cooling air in the fuel storage chamber 2 to be freely set.
[0023]
In the present embodiment, since the casing of the roof 30 supported by the side wall 20 can be thickened, the protection against external flying objects, which has been conventionally performed by the ceiling slab of the fuel storage chamber, is the ceiling of the fuel loading chamber 13, that is, This can be done with the roof 30. For this reason, it is not necessary to take a protective measure against an external flying object to the transport equipment for transporting the canister, specifically, the air pallet transport vehicle 16.
[0024]
In the above-described embodiment, the opening 23 is formed in the side wall 20, but it is possible to move between the fuel loading chambers (radioactive material loading chambers) 13 separated by the side wall 20 without forming the opening 23 in the side wall 20. Alternatively, a conveyance vehicle passage for the air pallet type conveyance vehicle 16 may be formed. In other words, the conveyance vehicle passage is provided between one end surface of the side wall 20 and the side wall forming the air inflow passage 6 (between the other end surface of the side wall 20 or another side wall forming the air discharge passage 7). Form. The opening 23 described above is also a conveyance vehicle passage.
[0025]
In the embodiment described above, a plurality of fuel loading chambers 13 partitioned by the side walls 20 are formed above the plurality of fuel storage chambers 2, but one wide area without the side walls 20 above the plurality of fuel storage chambers 2. A fuel loading chamber may be formed. In this case, the roof 30 is supported by a plurality of columns installed directly above the side wall 21 (on the extension line of the side wall 21) instead of the side wall 20. At least one of the intervals between the plurality of columns installed just above one side wall 21 may be a width that allows the air pallet transport vehicle 16 to pass between the two columns forming the interval. . It can be said that a conveyance vehicle passage is formed between two pillars having a width through which the air pallet type conveyance vehicle 16 can pass.
[0026]
Moreover, although the radioactive substance dry-type storage building 1 demonstrated taking the case of storing a spent fuel assembly as an example, instead of a spent fuel assembly, radioactive waste solidified bodies, such as a glass solidified body of a high level radioactive waste This can also be applied to the case of storing in the storage tube 5.
[0027]
【The invention's effect】
According to the present invention, the side walls provided between the fuel loading chambers support the roof, and the lightweight air pallet type transport vehicle is used . Therefore, the structure of the radioactive material dry storage building roof can be simplified.
[Brief description of the drawings]
1 is a longitudinal sectional view (II sectional view of FIGS. 2 and 3) of a radioactive substance dry storage building according to a preferred embodiment of the present invention;
FIG. 2 is a cross-sectional view taken along the line II-II in FIG.
3 is a cross-sectional view taken along the line III-III in FIG.
4 is a cross-sectional view taken along the line IV-IV in FIGS. 2 and 3. FIG.
[Explanation of symbols]
DESCRIPTION OF SYMBOLS 1 ... Radioactive material dry-type storage building, 2 ... Fuel storage room, 3 ... Ceiling slab, 4 ... Floor slab, 5 ... Storage pipe, 6 ... Air inflow passage, 7 ... Air discharge passage, 10 ... Partition member, 13 ... Fuel loading Chamber 16, air pallet type carriage 20, 21 side wall 23, opening 23, air pallet 26, hoisting device 28, upper cooling channel 29, lower cooling channel 44, canister housing casing .

Claims (1)

互いに側壁で分離され、放射性物質を収納する複数の収納管が配置される複数の放射性物質貯蔵室と、前記放射性物質貯蔵室に連絡され、外部の空気を前記放射性物質貯蔵室に供給する空気流入通路と、前記放射性物質貯蔵室に連絡され、前記放射性物質貯蔵室内の前記空気を排出する空気排出通路と、前記放射性物質貯蔵室の上方に形成され、エアパレットを有する放射性物質搬送手段が移動する放射性物質装荷領域と、前記放射性物質装荷領域を覆う屋根とを備え、前記放射性物質搬送手段が通過できる開口部を有すると共に前記屋根を支持する第2の側壁によって、複数の前記放射性物質装荷領域に分離され、前記第2の側壁が、隣接する前記放射性物質貯蔵室相互間に形成される前記側壁の延長線上で前記放射性物質装荷領域の床面上に配置されていることを特徴とする放射性物質乾式貯蔵建屋。A plurality of radioactive material storage chambers separated from each other by a side wall and arranged with a plurality of storage tubes for storing radioactive materials, and an air inflow connected to the radioactive material storage chamber and supplying external air to the radioactive material storage chamber A radioactive material conveying means having an air pallet, which is formed above the radioactive material storage chamber, is connected to the passage, the radioactive material storage chamber and discharges the air in the radioactive material storage chamber, and moves. A radioactive material loading area and a roof that covers the radioactive material loading area, and having an opening through which the radioactive substance conveying means can pass, and a plurality of radioactive substance loading areas by a second side wall that supports the roof. It is separated, the second side wall, the floor of the radioactive substance loading area on the extension of the side wall formed between the radioactive substance storage chamber mutually adjacent It radioactive material dry storage building, characterized in that disposed.
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