JPH10153684A - Fuel handling device - Google Patents
Fuel handling deviceInfo
- Publication number
- JPH10153684A JPH10153684A JP8310535A JP31053596A JPH10153684A JP H10153684 A JPH10153684 A JP H10153684A JP 8310535 A JP8310535 A JP 8310535A JP 31053596 A JP31053596 A JP 31053596A JP H10153684 A JPH10153684 A JP H10153684A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- shielding
- mox
- radiation
- length
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
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)
Abstract
(57)【要約】
【課題】本発明の目的は、原子炉建屋内におけるMOX
燃料の移動作業時に、比較的単純な構造で、作業性を悪
化させずに作業者の被曝低減を図ることのできる燃料取
扱装置を提供することにある。
【解決手段】燃料取扱装置1は、MOX燃料を吊り下げ
る燃料吊下部10,MOX燃料から放出される放射線を
遮蔽するための放射線遮蔽部20,燃料吊下部10をワ
イヤー40で吊り下げると共に放射線遮蔽部20をワイ
ヤー50で吊り下げるベース30などから構成される。
放射線遮蔽部20は、5種類の遮蔽要素が同心状に多層
に構成されている。各遮蔽要素は隣り合う遮蔽要素と互
いに接続され、放射線遮蔽部20の鉛直方向の長さが伸
縮自在となるように構成されている。
(57) [Summary] An object of the present invention is to provide MOX in a reactor building.
It is an object of the present invention to provide a fuel handling apparatus which has a relatively simple structure at the time of fuel transfer operation and which can reduce the exposure of workers without deteriorating workability. A fuel handling device (1) suspends a MOX fuel, a radiation shield (20) for shielding radiation emitted from the MOX fuel, and a fuel suspension (10) suspended by a wire (40) and a radiation shield. The unit 20 includes a base 30 suspended by a wire 50.
The radiation shielding unit 20 includes five types of shielding elements concentrically arranged in a multilayer. Each shielding element is connected to an adjacent shielding element, and is configured such that the vertical length of the radiation shielding unit 20 can be expanded and contracted.
Description
【0001】[0001]
【発明の属する技術分野】本発明は原子力プラントの原
子炉建屋内における燃料集合体の取扱装置に係わり、特
にプルトニウム酸化物とウラン酸化物の混合燃料が含ま
れる混合燃料集合体(以下、MOX燃料という)を原子
炉建屋内で移動させるのに好適な燃料取扱装置に関す
る。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly handling apparatus in a reactor building of a nuclear power plant, and more particularly to a mixed fuel assembly containing a mixed fuel of plutonium oxide and uranium oxide (hereinafter referred to as MOX fuel). ) Within a reactor building.
【0002】[0002]
【従来の技術】一般に、軽水型原子炉の一例である沸騰
水型原子炉では、ウラン酸化物燃料集合体(以下、ウラ
ン燃料という)は専用の輸送容器に収納されて発電所内
に搬入された後、輸送容器から取り出されて燃料検査が
行われ、チャンネルボックスが取り付けられた状態で一
時的に使用済燃料プールなどの貯蔵施設に保管された
後、原子炉内に装荷される。2. Description of the Related Art Generally, in a boiling water reactor which is an example of a light water reactor, a uranium oxide fuel assembly (hereinafter referred to as uranium fuel) is housed in a dedicated transport container and carried into a power plant. Thereafter, the fuel cell is taken out of the transport container and subjected to a fuel inspection, temporarily stored in a storage facility such as a spent fuel pool with the channel box attached, and then loaded into the nuclear reactor.
【0003】ウラン燃料の場合、燃料集合体から放出さ
れる放射線の線量率が低いため、上記従来の燃料取扱作
業においては、特に放射線を防護するための遮蔽設備を
設けずに取り扱うことができた。[0003] In the case of uranium fuel, since the dose rate of radiation emitted from the fuel assembly is low, the conventional fuel handling operation described above could be handled without providing a shielding facility for protecting radiation in particular. .
【0004】また、使用済燃料の輸送容器に関する従来
技術として、特開昭56−26294 号公報及び特開昭61−38
600 号公報に、使用済燃料から放出される中性子の遮蔽
及び使用済燃料から発生する崩壊熱の除去のための水を
内部に密封した輸送容器が記載されている。更に、特開
昭61−38600 号公報には、輸送容器の外面の汚染を防止
するために、輸送容器の外側を覆い水に対するシール機
構を備えた汚染防止装置が記載されている。[0004] Further, as prior art relating to a container for transporting spent fuel, Japanese Patent Application Laid-Open Nos. 56-26294 and 61-38 are disclosed.
No. 600 describes a transport container in which water is sealed inside for shielding neutrons emitted from spent fuel and removing decay heat generated from spent fuel. Further, Japanese Patent Application Laid-Open No. 61-38600 describes a pollution control device which covers the outside of a transport container and is provided with a seal mechanism for water in order to prevent the outer surface of the transport container from being contaminated.
【0005】[0005]
【発明が解決しようとする課題】従来のウラン燃料の取
扱作業に比べて、MOX燃料の場合は以下の課題が懸念
される。MOX燃料はウラン燃料に比べて燃料集合体か
ら放出される放射線の線量率が比較的高いので、作業者
の被曝低減を考慮する必要がある。このためには、作業
従事時間の限定などの作業性の悪化が余儀なくされる。[0005] Compared with the conventional uranium fuel handling operation, the following problems are more likely to occur with MOX fuel. Since the MOX fuel has a relatively high dose rate of radiation emitted from the fuel assembly as compared with the uranium fuel, it is necessary to consider the reduction of worker exposure. For this reason, the workability is inevitably degraded, such as the limitation of work hours.
【0006】また、特開昭56−26294号公報及び特開昭6
1−38600号公報に記載された輸送容器では内部に水を密
封する必要があるため取扱いが煩雑になり、使用前燃料
を取り扱う場合には適さない。更に、特開昭61−38600
号公報に記載された汚染防止装置ではこの装置自体に放
射線に対する遮蔽機能はないし、水に対するシール機構
を備える必要があるため構造が複雑になる。Further, Japanese Patent Application Laid-Open Nos. Sho 56-26294 and
In the transport container described in JP-A-38600, it is necessary to seal water inside, so that handling becomes complicated, and it is not suitable for handling fuel before use. Further, JP-A-61-38600
In the pollution prevention device described in the publication, the device itself does not have a function of shielding against radiation and needs to have a sealing mechanism for water, so that the structure becomes complicated.
【0007】本発明の目的は、原子炉建屋内におけるM
OX燃料の移動作業時に、比較的単純な構造で、作業性
を悪化させずに作業者の被曝低減を図ることのできる燃
料取扱装置を提供することにある。It is an object of the present invention to provide an M
It is an object of the present invention to provide a fuel handling device which can reduce the exposure of an operator without deteriorating the workability with a relatively simple structure at the time of the OX fuel transfer operation.
【0008】[0008]
【課題を解決するための手段】上記目的を達成するため
の第1の発明は、MOX燃料集合体を吊り下げるための
第1吊下部と、MOX燃料集合体から放出される放射線
を遮蔽する複数の遮蔽材を同心状に多層に構成した放射
線遮蔽部と、前記第1吊下部及び前記放射線遮蔽部を吊
り下げる第2吊下部とを備え、前記第2吊下部で前記第
1吊下部を鉛直上方に吊り上げることにより前記放射線
遮蔽部の鉛直方向の長さが伸びるように前記複数の遮蔽
材は互いに接続され、伸びた状態における前記放射線遮
蔽部の長さはMOX燃料集合体のほぼ全長を覆う長さ以
上であるように構成する。Means for Solving the Problems A first invention for achieving the above object is a first suspension for suspending a MOX fuel assembly, and a plurality of suspensions for shielding radiation emitted from the MOX fuel assembly. A radiation shielding portion in which a plurality of shielding members are concentrically configured, and a second suspension portion suspending the first suspension portion and the radiation shielding portion, wherein the second suspension portion vertically extends the first suspension portion. The plurality of shielding members are connected to each other such that the radiation shielding portion is extended in a vertical direction by being lifted upward, and the length of the radiation shielding portion in the extended state covers almost the entire length of the MOX fuel assembly. It is configured to be longer than the length.
【0009】また、上記目的を達成するための第2の発
明は、MOX燃料集合体を吊り下げるための燃料吊下部
と、MOX燃料集合体から放出される放射線を遮蔽し且
つその長さがMOX燃料集合体のほぼ全長を覆う長さ以
上である放射線遮蔽部とを備える。According to a second aspect of the present invention, there is provided a fuel suspension for suspending a MOX fuel assembly, and a shield for shielding radiation emitted from the MOX fuel assembly and having a length of MOX. A radiation shielding portion having a length that is equal to or greater than a length covering substantially the entire length of the fuel assembly.
【0010】[0010]
【発明の実施の形態】以下、本発明による燃料取扱装置
の一実施例を図1〜図3を用いて説明する。図1は本発
明による燃料取扱装置の概略構成図、図2は図1の装置
で燃料輸送容器からMOX燃料を取り出す過程の説明
図、図3は原子炉建屋内における燃料取扱作業の一例を
示すフローチャートである。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS One embodiment of a fuel handling apparatus according to the present invention will be described below with reference to FIGS. FIG. 1 is a schematic configuration diagram of a fuel handling apparatus according to the present invention, FIG. 2 is an explanatory view of a process of removing MOX fuel from a fuel transport container by the apparatus of FIG. 1, and FIG. 3 shows an example of a fuel handling operation in a reactor building. It is a flowchart.
【0011】図3の燃料取扱作業は、原子炉建屋内への
燃料輸送容器の搬入からMOX燃料を原子炉へ装荷する
までの燃料取扱を示している。図3の燃料取扱作業のう
ち本発明による燃料取扱装置を用いる作業は、ステップ
3A〜6A,ステップ8A〜10A、及びステップ12
A〜14Aに関する作業である。The fuel handling operation shown in FIG. 3 shows the fuel handling from loading the fuel transport container into the reactor building to loading MOX fuel into the reactor. The operation using the fuel handling apparatus according to the present invention in the fuel handling operation of FIG. 3 includes steps 3A to 6A, steps 8A to 10A, and step 12A.
A to 14A.
【0012】ステップ3A〜6AはMOX燃料を収納し
た燃料ホルダを燃料輸送容器から取り出して燃料起立台
に設置するまでの作業であり、燃料ホルダを燃料起立台
に設置する直前又は直後に燃料取扱装置は燃料ホルダか
ら取り外される。ステップ8A〜10Aは燃料ホルダか
ら取り出されたMOX燃料を燃料起立台から燃料検査台
まで移動させて設置するまでの作業であり、MOX燃料
を燃料検査台に設置する直前又は直後に燃料取扱装置は
MOX燃料から取り外される。ステップ12A〜14Aは
検査が終了したMOX燃料を燃料検査台からチャンネル
着脱機まで移動させて設置するまでの作業であり、MO
X燃料をチャンネル着脱機に設置する直前又は直後に燃
料取扱装置はMOX燃料から取り外される。Steps 3A to 6A are operations until the fuel holder containing the MOX fuel is taken out of the fuel transport container and placed on the fuel stand, and immediately before or immediately after the fuel holder is placed on the fuel stand, Is removed from the fuel holder. Steps 8A to 10A are operations for moving the MOX fuel taken out from the fuel holder from the fuel stand to the fuel inspection table and installing the same. The fuel handling device is operated immediately before or immediately after the MOX fuel is installed on the fuel inspection table. Removed from MOX fuel. Steps 12A to 14A are operations for moving the MOX fuel which has been inspected from the fuel inspection table to the channel attaching / detaching machine and installing the same.
Immediately before or immediately after the X fuel is installed in the channel detacher, the fuel handling device is removed from the MOX fuel.
【0013】以下、ステップ3A〜4Aの燃料取扱作業
に関連付けて、本実施例の燃料取扱装置の構成を説明す
る。本実施例の燃料取扱装置1は、MOX燃料を吊り下
げる燃料吊下部10、MOX燃料から放出される放射線
を遮蔽するための放射線遮蔽部20、燃料吊下部10を
ワイヤー40で吊り下げると共に放射線遮蔽部20をワ
イヤー50で吊り下げるベース30などから構成され
る。Hereinafter, the configuration of the fuel handling apparatus according to the present embodiment will be described in relation to the fuel handling operation in steps 3A to 4A. The fuel handling apparatus 1 according to the present embodiment includes a fuel suspension 10 for suspending MOX fuel, a radiation shielding unit 20 for shielding radiation emitted from the MOX fuel, a fuel suspension 10 suspended by a wire 40 and radiation shielding. The unit 20 includes a base 30 suspended by a wire 50.
【0014】放射線遮蔽部20は、5種類の遮蔽要素2
0a〜20eが同心状に多層に構成されている。各遮蔽
要素は隣り合う遮蔽要素と互いに接続され、図2に示す
ように、放射線遮蔽部20の鉛直方向(上下方向)の長
さが伸縮自在となるように構成されている。隣り合う遮
蔽要素間の接続方法としては、例えば鉛直方向に長い溝
と凸部のはめ合い機構を周方向に等間隔に複数設ける方
法などを採用できる。このような機構を用いることによ
り、燃料取扱装置の構造を比較的単純にできる。The radiation shielding section 20 includes five types of shielding elements 2
0a to 20e are concentrically formed in multiple layers. Each shielding element is connected to an adjacent shielding element, and as shown in FIG. 2, is configured such that the length of the radiation shielding unit 20 in the vertical direction (vertical direction) can be expanded and contracted. As a connection method between adjacent shielding elements, for example, a method of providing a plurality of fitting mechanisms of a vertically long groove and a convex portion at equal intervals in a circumferential direction can be adopted. By using such a mechanism, the structure of the fuel handling device can be made relatively simple.
【0015】各遮蔽要素は概ね円筒形状又は角筒形状を
しており、遮蔽要素20aはその下端に燃料輸送容器1
05の燃料取出口105aに挿入可能な突出部21を有
し、遮蔽要素20eはその上端に燃料吊下部10と係合
する係合部23を有する。遮蔽要素20aは、更に燃料
の水平方向のぶれを防止するための燃料保持機構22を
内側に有する。Each shielding element has a substantially cylindrical or rectangular cylindrical shape, and the shielding element 20a has a fuel transport container 1 at its lower end.
05 has a protruding portion 21 which can be inserted into the fuel outlet 105a, and the shielding element 20e has an engaging portion 23 which engages with the fuel suspension 10 at the upper end thereof. The shielding element 20a further has a fuel holding mechanism 22 for preventing horizontal displacement of the fuel inside.
【0016】遮蔽要素はMOX燃料から放出される中性
子線やγ線などの放射線を遮蔽するためのものであり、
遮蔽要素の外側における線量率を十分に低減できるもの
を選ぶ。遮蔽要素の材料としては、具体的には、ポリエ
チレンなどの高分子化合物、鉛やステンレス鋼などの金
属材料、又はこれらを組み合わせたものを用いることが
できる。The shielding element is for shielding radiation such as neutrons and gamma rays emitted from the MOX fuel,
Select one that can sufficiently reduce the dose rate outside the shielding element. As the material of the shielding element, specifically, a polymer compound such as polyethylene, a metal material such as lead or stainless steel, or a combination thereof can be used.
【0017】ベース30はワイヤー50の鉛直方向の長
さを調整するためのワイヤー駆動部31を有し、放射線
遮蔽部20が長く伸びる際にワイヤー50の長さを伸ば
し、放射線遮蔽部20が短く縮む際にワイヤー50の長
さを縮めるように制御される。The base 30 has a wire driving unit 31 for adjusting the length of the wire 50 in the vertical direction. When the radiation shielding unit 20 is elongated, the length of the wire 50 is increased, and the radiation shielding unit 20 is shortened. At the time of contraction, the length of the wire 50 is controlled to be reduced.
【0018】次に、図2を用いて燃料輸送容器105か
らMOX燃料を収納した燃料ホルダ101を取り出す過
程を説明する。図2(a)に示すように、放射線遮蔽部
20の鉛直方向の長さを短くした状態で遮蔽要素20a
の突出部21を燃料輸送容器105の燃料取出口105
aに挿入し、燃料吊下部10により燃料ホルダ101を
吊り上げる。燃料吊下部10には、燃料ホルダ101の
ハンドルをつかむ把持機構などを用いることができる。Next, a process of taking out the fuel holder 101 containing the MOX fuel from the fuel transport container 105 will be described with reference to FIG. As shown in FIG. 2A, the shielding element 20a is set in a state where the vertical length of the radiation shielding unit 20 is reduced.
Of the fuel outlet 105 of the fuel transport container 105
a, and the fuel holder 101 is lifted by the fuel hanging portion 10. For the fuel suspension 10, a gripping mechanism or the like for grasping the handle of the fuel holder 101 can be used.
【0019】図2(a)の状態から、原子炉建屋内の天
井クレーン104によりワイヤー104aを介してベー
ス30を吊り上げながら、ワイヤー駆動部31によりワ
イヤー50の長さを伸ばす。燃料吊下部10が吊り上げ
られ遮蔽要素20eと係合した後は、図2(b)に示す
ように、燃料吊下部10の上方移動に伴い内側の遮蔽要
素20eから順に上方へ移動する。In the state shown in FIG. 2A, the length of the wire 50 is extended by the wire driving unit 31 while the base 30 is lifted by the overhead crane 104 in the reactor building via the wire 104a. After the fuel suspension 10 is lifted and engaged with the shielding element 20e, as shown in FIG. 2B, the fuel suspension 10 moves upward in order from the inner shielding element 20e as the fuel suspension 10 moves upward.
【0020】燃料吊下部10により燃料ホルダ101を
吊り上げていく最中も、燃料保持機構22は燃料ホルダ
101を水平方向に保持し続ける。燃料保持機構22は
その先端に弾性部材22aを有し、弾性部材22aが備
える弾性力によって燃料ホルダ101の水平方向のぶれ
を抑制する。このようにして、燃料ホルダ101を燃料
輸送容器105から取り出した状態を図2(c)に示
す。燃料ホルダ101から燃料取扱装置を取り外す場合
は、以上と逆の手順で行えば良い。The fuel holding mechanism 22 keeps holding the fuel holder 101 horizontally even while the fuel holder 101 is being lifted by the fuel hanging part 10. The fuel holding mechanism 22 has an elastic member 22a at its tip, and suppresses horizontal displacement of the fuel holder 101 by the elastic force of the elastic member 22a. FIG. 2C shows a state where the fuel holder 101 is taken out of the fuel transport container 105 in this manner. When removing the fuel handling device from the fuel holder 101, the procedure may be reversed.
【0021】図2(c)に示すように、放射線遮蔽部2
0が伸びた状態において、放射線遮蔽部20の長さは燃
料ホルダ101の全長を覆うように設定されている。こ
のように、放射線遮蔽部20はその下端部を除いて燃料
ホルダ101を完全に覆うことができる。これにより、
燃料ホルダ101の移動中も、放射線遮蔽部20は燃料
ホルダ101から放出される放射線を十分に遮蔽するこ
とができる。As shown in FIG. 2C, the radiation shielding unit 2
In a state where 0 is extended, the length of the radiation shielding section 20 is set so as to cover the entire length of the fuel holder 101. As described above, the radiation shielding portion 20 can completely cover the fuel holder 101 except for the lower end portion. This allows
The radiation shielding unit 20 can sufficiently shield the radiation emitted from the fuel holder 101 even while the fuel holder 101 is moving.
【0022】本実施例によれば、放射線遮蔽部20を多
層の遮蔽要素20a〜20eで伸縮自在に構成したこと
により、燃料取扱装置を燃料ホルダ101に取り付ける
際に燃料取扱装置の全長を必要最小限に短尺化できるの
で、取付作業を容易に行うことができる。According to the present embodiment, since the radiation shielding section 20 is configured to be expandable and contractible by the multilayer shielding elements 20a to 20e, the total length of the fuel handling apparatus can be minimized when the fuel handling apparatus is mounted on the fuel holder 101. Since the length can be shortened as much as possible, the mounting operation can be easily performed.
【0023】本燃料取扱装置で、ステップ8A〜10A
及びステップ12A〜14AのMOX燃料を取り扱う場合
は、燃料吊下部10でMOX燃料を直接吊ることにな
る。従って、燃料保持機構22は燃料ホルダ及びMOX
燃料の両方を水平方向に保持できるように構成されてい
る。In this fuel handling apparatus, steps 8A to 10A
When handling the MOX fuel in steps 12A to 14A, the MOX fuel is directly suspended by the fuel suspension 10. Therefore, the fuel holding mechanism 22 is connected to the fuel holder and the MOX.
It is configured so that both fuels can be held in the horizontal direction.
【0024】本実施例によれば、燃料輸送容器からのM
OX燃料の移動などの原子炉建屋内におけるMOX燃料
の移動作業時においても、MOX燃料から放出される放
射線が十分に遮蔽された環境で作業できるので、作業者
の被曝低減を図ることができる。これに伴ってMOX燃
料をウラン燃料と同じように扱えるので、作業性を悪化
させずに済む。また、遮蔽要素間の接続機構としては通
常のはめ合い機構などを容易に適用できるので、比較的
単純な構造にできる。According to the present embodiment, M
Even when the MOX fuel is moved inside the reactor building, such as when the OX fuel is moved, it is possible to work in an environment where the radiation emitted from the MOX fuel is sufficiently shielded, so that it is possible to reduce the exposure of the worker. Accordingly, the MOX fuel can be handled in the same manner as the uranium fuel, so that the workability does not deteriorate. Further, since a normal fitting mechanism or the like can be easily applied as a connection mechanism between the shielding elements, a relatively simple structure can be achieved.
【0025】尚、本実施例では放射線遮蔽部20として
伸縮可能な構造のものを説明したが、放射線遮蔽部20
は長さが固定されたものであっても良い。この場合も、
図2(c)のように、放射線遮蔽部20は燃料吊下部1
0と上端で係合し、燃料ホルダ又はMOX燃料を水平方
向に保持する燃料保持機構22を備え、燃料ホルダ又は
MOX燃料のほぼ全長を覆う長さを有していれば、同様
な効果を得ることができる。固定型の場合、上記実施例
のような伸縮機構が不要となるので、構造はより単純と
なる。但し、全長が長くなった分、多少取扱い難くな
る。In the present embodiment, the radiation shielding section 20 is described as having an expandable and contractible structure.
May have a fixed length. Again,
As shown in FIG. 2 (c), the radiation shielding unit 20 is
A similar effect can be obtained by providing a fuel holding mechanism 22 that engages at the upper end with 0 and holds the fuel holder or MOX fuel in the horizontal direction and has a length that covers substantially the entire length of the fuel holder or MOX fuel. be able to. In the case of the fixed type, the structure is simpler because the expansion and contraction mechanism as in the above embodiment is unnecessary. However, it becomes somewhat difficult to handle because the total length is longer.
【0026】[0026]
【発明の効果】本発明によれば、原子炉建屋内における
MOX燃料の移動作業時においても、比較的単純な構造
の燃料取扱装置で、作業性を悪化させずに作業者の被曝
低減を図ることができる。According to the present invention, even when the MOX fuel is moved inside the reactor building, the exposure of the worker can be reduced without deteriorating the workability with the fuel handling device having a relatively simple structure. be able to.
【図1】本発明による燃料取扱装置の概略構成図。FIG. 1 is a schematic configuration diagram of a fuel handling device according to the present invention.
【図2】図1の装置で燃料輸送容器からMOX燃料を取
り出す過程の説明図。FIG. 2 is an explanatory view of a process of taking out MOX fuel from a fuel transport container by the apparatus of FIG. 1;
【図3】原子炉建屋内における燃料取扱作業の一例を示
すフローチャート。FIG. 3 is a flowchart showing an example of a fuel handling operation in a reactor building.
1…燃料取扱装置、10…燃料吊下部、20…放射線遮
蔽部、20a〜20e…遮蔽要素、21…突出部、22
…燃料保持機構、22a…弾性部材、23…係合部、3
0…ベース、31…ワイヤー駆動部、40,50…ワイ
ヤー、101…燃料ホルダ、105…燃料輸送容器。DESCRIPTION OF SYMBOLS 1 ... Fuel handling apparatus, 10 ... Fuel suspension part, 20 ... Radiation shielding part, 20a-20e ... Shielding element, 21 ... Projection part, 22
... Fuel holding mechanism, 22a ... elastic member, 23 ... engaging part, 3
0: Base, 31: Wire drive unit, 40, 50: Wire, 101: Fuel holder, 105: Fuel transport container.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 高久 和夫 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 奥田 慎一 茨城県日立市幸町三丁目2番1号 日立エ ンジニアリング株式会社内 (72)発明者 福沢 宏幸 茨城県日立市幸町三丁目2番2号 株式会 社日立エンジニアリングサービス内 (72)発明者 飯田 耕司 茨城県日立市幸町三丁目2番2号 株式会 社日立エンジニアリングサービス内 (72)発明者 川田 能成 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Kazuo Takaku 3-1-1, Sachimachi, Hitachi-shi, Ibaraki Pref. Hitachi, Ltd. Hitachi Plant, Ltd. (72) Shinichi Okuda 3-1-2 Sachimachi, Hitachi-shi, Ibaraki No. 1 Inside Hitachi Engineering Co., Ltd. (72) Inventor Hiroyuki Fukuzawa 3-2-2 Samachi, Hitachi City, Ibaraki Prefecture Inside Hitachi Engineering Services Co., Ltd. (72) Koji Iida Inventor Koji Samachi, Hitachi City, Ibaraki Prefecture Hitachi Engineering Services Co., Ltd. (2-2) Inventor Yoshinari Kawada 3-1-1, Kochicho, Hitachi-shi, Ibaraki Pref. Hitachi, Ltd. Hitachi Plant
Claims (3)
吊下部と、MOX燃料集合体から放出される放射線を遮
蔽する複数の遮蔽材を同心状に多層に構成した放射線遮
蔽部と、前記第1吊下部及び前記放射線遮蔽部を吊り下
げる第2吊下部とを備え、 前記第2吊下部で前記第1吊下部を鉛直上方に吊り上げ
ることにより前記放射線遮蔽部の鉛直方向の長さが伸び
るように前記複数の遮蔽材は互いに接続され、 伸びた状態における前記放射線遮蔽部の長さはMOX燃
料集合体のほぼ全長を覆う長さ以上であることを特徴と
する燃料取扱装置。1. A first method for suspending a MOX fuel assembly.
A hanging portion, a radiation shielding portion in which a plurality of shielding materials for shielding radiation emitted from the MOX fuel assembly are concentrically arranged in a multilayer, and a second hanging portion for suspending the first hanging portion and the radiation shielding portion. The plurality of shielding members are connected to each other such that the first hanging portion is vertically lifted by the second hanging portion so that the length of the radiation shielding portion in the vertical direction is extended. The fuel handling device according to claim 1, wherein a length of the radiation shielding portion is equal to or longer than a length covering substantially the entire length of the MOX fuel assembly.
吊下部と、MOX燃料集合体から放出される放射線を遮
蔽し且つその長さがMOX燃料集合体のほぼ全長を覆う
長さ以上である放射線遮蔽部とを備えたことを特徴とす
る燃料取扱装置。2. A fuel suspension for suspending a MOX fuel assembly, and a length that shields radiation emitted from the MOX fuel assembly and has a length equal to or greater than a length covering substantially the entire length of the MOX fuel assembly. A fuel handling device comprising: a radiation shielding part.
部は前記MOX燃料集合体の水平方向の移動を抑制する
手段を備えたことを特徴とする燃料取扱装置。3. The fuel handling apparatus according to claim 1, wherein the radiation shielding unit includes a unit for suppressing the horizontal movement of the MOX fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8310535A JPH10153684A (en) | 1996-11-21 | 1996-11-21 | Fuel handling device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8310535A JPH10153684A (en) | 1996-11-21 | 1996-11-21 | Fuel handling device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH10153684A true JPH10153684A (en) | 1998-06-09 |
Family
ID=18006411
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8310535A Pending JPH10153684A (en) | 1996-11-21 | 1996-11-21 | Fuel handling device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH10153684A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007271511A (en) * | 2006-03-31 | 2007-10-18 | Toshiba Corp | Reactor fuel changer |
-
1996
- 1996-11-21 JP JP8310535A patent/JPH10153684A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007271511A (en) * | 2006-03-31 | 2007-10-18 | Toshiba Corp | Reactor fuel changer |
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