JPH0220718Y2 - - Google Patents

Info

Publication number
JPH0220718Y2
JPH0220718Y2 JP1983078918U JP7891883U JPH0220718Y2 JP H0220718 Y2 JPH0220718 Y2 JP H0220718Y2 JP 1983078918 U JP1983078918 U JP 1983078918U JP 7891883 U JP7891883 U JP 7891883U JP H0220718 Y2 JPH0220718 Y2 JP H0220718Y2
Authority
JP
Japan
Prior art keywords
heating
shipping
bottom plate
attached
jacket
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
Application number
JP1983078918U
Other languages
Japanese (ja)
Other versions
JPS59185697U (en
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed filed Critical
Priority to JP1983078918U priority Critical patent/JPS59185697U/en
Publication of JPS59185697U publication Critical patent/JPS59185697U/en
Application granted granted Critical
Publication of JPH0220718Y2 publication Critical patent/JPH0220718Y2/ja
Granted legal-status Critical Current

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Classifications

    • 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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 この考案は原子燃料集合体の破損の有無を検出
するために用いられるシツピング装置のシツピン
グキヤンの改良に関する。
DETAILED DESCRIPTION OF THE INVENTION This invention relates to an improvement in the shipping can of a shipping device used to detect the presence or absence of damage in a nuclear fuel assembly.

原子炉内で使用されている核燃料集合体の中に
は、原子炉の継続的な運転によつて一部の燃料棒
に破損やピンホールを生じ、内部に発生した核分
裂生成物を漏出するものがあり、このような燃料
集合体はまだ寿命が残つていたにしても、安全上
の面から使用することができず、したがつて、ど
の燃料集合体が破損しているか否かを知る必要が
あり、燃料集合体の定期的な検査が行われてい
る。
In nuclear fuel assemblies used in nuclear reactors, some fuel rods may become damaged or pinhole due to continuous operation of the reactor, causing fission products generated inside to leak out. Even if such fuel assemblies still have some life remaining, they cannot be used for safety reasons, and therefore it is difficult to know which fuel assemblies are damaged or not. It is necessary and regular inspections of fuel assemblies are carried out.

この検査は、一般に燃料集合体を貯蔵プールに
収容して行われるが、水中テレビカメラで確認で
きないものについては、通常第1図のようなシツ
ピング手段が採用されている。
This inspection is generally carried out by storing the fuel assembly in a storage pool, but if the fuel assembly cannot be confirmed with an underwater television camera, shipping means as shown in Fig. 1 is usually adopted.

すなわち、第1図のように周囲に電気ヒータh
を内装したエアジヤケツトbを設けたシツピング
キヤンaを貯蔵プールP中に配設し、検査すべき
燃料集合体nをそのシツピングキヤンaに収容
し、周囲のエアジヤケツトbにジヤケツトガス
(通常窒素ガス)を送り込み、中のプール水を追
い出して断熱層を形成し、その断熱層の作用によ
つて集合体の組成燃料の自己発熱により内部ガス
を熱膨張させて被覆管の破損箇所から漏出させ、
これをキヤンの下側から送り込んだキヤリアガス
(ジヤケツトガスに同じ)で連行し、放射線検出
器Bにより放射能の多寡を検出し、破損の有無を
確認するようにしている。
That is, as shown in Figure 1, there is an electric heater h around the
A shipping can a equipped with an air jacket b containing a fuel assembly is placed in a storage pool P, a fuel assembly n to be inspected is stored in the shipping can a, and a jacket gas (usually nitrogen gas) is injected into the surrounding air jacket b. A heat insulating layer is formed by expelling the pool water inside, and due to the action of the heat insulating layer, the internal gas is thermally expanded due to self-heating of the fuel composition of the assembly, causing it to leak from the damaged part of the cladding.
This is carried away by carrier gas (same as jacket gas) fed from the bottom of the can, and radiation detector B detects the amount of radioactivity to check for damage.

しかし、貯蔵プールP中に長期に保管された燃
料集合体nでは自己発熱能力が低下しているもの
があり、その場合にはエアジヤケツトb中の電気
ヒータhに通電し、エアジヤケツトbを介して燃
料集合体nを強制加熱し、核分裂生成物の漏出を
促進させるようにしている。
However, some fuel assemblies n that have been stored for a long time in the storage pool P have reduced self-heating ability, and in that case, the electric heater h in the air jacket b is energized and the fuel is supplied through the air jacket b. The assembly n is forcibly heated to promote leakage of fission products.

ところで、これまでの加熱手段は二重キヤンに
なつたエアジヤケツトbの内壁上に固着されてい
て、キヤンを壊さなければ取外しができないた
め、絶縁性の検査や破損箇所の修理ならびに清掃
などのメンテナンスが殆んどできないという難点
がある。
By the way, conventional heating means are fixed to the inner wall of air jacket b, which has a double can, and cannot be removed without breaking the can, so maintenance such as testing insulation, repairing damaged parts, and cleaning is difficult. The problem is that it is almost impossible to do.

そこで、この考案は上記の実情に鑑み工夫され
たもので、キヤン本体を破損することなく加熱手
段の取付け、取外しが容易にでき、したがつてメ
ンテナンスを定期的に行うことができ、長期の使
用に耐えるシツピングキヤンを提供するものであ
り、外キヤンと内キヤンおよび両キヤンの間に形
成されたジヤケツト室からなり、ジヤケツト室内
に加熱部材を配設し、内キヤン中に収容した原子
燃料集合体を加熱して核分裂生成物を漏出させ、
破損の有無を検出するようにしたシツピング装置
において、底板の四方周囲部に上記内キヤンの周
囲表面がほぼ長手方向中央部に位置するようにし
て所要長さの長孔をそれぞれ設け、上記加熱部材
を長孔より若干大きな基板とこれに所要高さに立
設した複数の電熱線とで形成し、該電熱線を各長
孔を介して内キヤンの周面上に添設し、その上端
部を帯板ばねで支持し、かつ基板を底板の下面に
止め部材により着脱自在に取付けたことを特徴と
している。
Therefore, this idea was devised in view of the above-mentioned circumstances.The heating means can be easily installed and removed without damaging the main body of the can, and maintenance can therefore be carried out regularly, allowing for long-term use. This system provides a shipping can that can withstand high temperatures, and consists of an outer can, an inner can, and a jacket chamber formed between both cans, with a heating member disposed in the jacket chamber, and a nuclear fuel assembly housed in the inner can. heats the body to leak fission products,
In a shipping device configured to detect the presence or absence of damage, elongated holes of a required length are provided in the four periphery portions of the bottom plate so that the peripheral surface of the inner can is located approximately at the center in the longitudinal direction, and the heating member is formed by a substrate slightly larger than the elongated hole and a plurality of heating wires set upright on the substrate at a required height, and the heating wires are attached to the circumferential surface of the inner can via each elongated hole, and the upper end thereof is is supported by a strip spring, and the board is detachably attached to the lower surface of the bottom plate by a stopper member.

以下図面を参照してこの考案の実施例について
説明する。
Embodiments of this invention will be described below with reference to the drawings.

第2図はシツピングキヤンの上半部を省略して
示しているが、1はステンレス鋼からなり、断面
角形で、周囲が外キヤン1aと内キヤン1bとで
二重キヤンに形成されており、上端には燃料集合
体nを出し入れするため、第1図の従来品と同様
に加熱部材の発熱量を調整するための温度センサ
ーSを垂設した屋根状のキヤツプがシリンダ機構
により開閉自在に取付けられており、そして外キ
ヤン1aと内キヤン1bとの間はジヤケツト室2
をなしていて、常時はプール水により満たされて
いるが、シツピング時には導管(第1図)を通じ
てジヤケツトガスが所要量圧送され、プール水の
一部を下側から追い出して随時断熱層を形成する
ようになされている。
Although Fig. 2 does not show the upper half of the shipping can, 1 is made of stainless steel, has a rectangular cross section, and is surrounded by an outer can 1a and an inner can 1b forming a double can. , At the upper end, in order to take in and take out the fuel assembly n, a roof-shaped cap with a vertical temperature sensor S for adjusting the calorific value of the heating member, similar to the conventional product shown in Fig. 1, can be opened and closed by a cylinder mechanism. The jacket chamber 2 is installed between the outer can 1a and the inner can 1b.
It is filled with pool water at all times, but during shipping, the required amount of jacket gas is pumped through the conduit (Figure 1) to expel some of the pool water from the bottom and form a heat insulating layer. is being done.

ところで、この考案ではシツピングキヤン1の
底部に溶接されている底板3には第3図イのよう
にキヤン中にプール水やキヤリアガスを導入する
中心通孔3aが設けられるとゝもに、その周囲部
四方には、キヤンの内管1bの各辺に沿いかつ各
辺より短くそして各辺の表面が図示斜線のように
ほぼ中央を通るようなやゝ幅広な長孔3bがそれ
ぞれ形成されており、各長孔3bの内外縁両側の
下面には同図ハのような二つ割りまたは三つ割り
した複数の弾性挟持具4が取付けられ、また、内
キヤン1bの各辺の表面には下端から管のほぼ1/
3高さの位置に複数の凹凸状に形成された帯板ば
ね5がそれぞれほぼ水平に取付けられている。
By the way, in this invention, the bottom plate 3 welded to the bottom of the shipping can 1 is provided with a central hole 3a for introducing pool water and carrier gas into the can as shown in Fig. 3A. On all four sides of the periphery, wide elongated holes 3b are formed along each side of the inner tube 1b of the can, shorter than each side, and with the surface of each side passing approximately through the center as indicated by diagonal lines in the figure. A plurality of elastic clamping tools 4 divided into two or three parts as shown in Figure C are attached to the lower surface of both the inner and outer edges of each elongated hole 3b, and a plurality of elastic clamping tools 4 are attached to the surface of each side of the inner can 1b from the lower end. Almost 1/ of the tube
A plurality of strip springs 5 each having a concave and convex shape are installed substantially horizontally at three height positions.

また、第3図ロは電熱線6と基板7とからなる
加熱部材を示すものであり、シース管に被覆され
た電熱線6は内キヤン1bの1/3高さ程度の逆u
字形に形成され、その複数(図では3個)のもの
が基板7の長手方向に並設されており、基板7は
ステンレス鋼からなり、キヤンの底板3に設けら
れた長孔3bよりも一回り大きく、その上面四隅
には、長孔3bの内外縁両側に設けられた弾性挟
持具4に係合する止め具7aが設けられている。
In addition, FIG. 3B shows a heating member consisting of a heating wire 6 and a substrate 7, and the heating wire 6 covered by the sheath tube is placed in an inverted U shape about 1/3 of the height of the inner can 1b.
A plurality of them (three in the figure) are arranged in parallel in the longitudinal direction of the substrate 7, and the substrate 7 is made of stainless steel, and is formed in the shape of a can. It has a large circumference, and at the four corners of its upper surface are provided stoppers 7a that engage with elastic clamping members 4 provided on both inner and outer edges of the elongated hole 3b.

そこで、底板3の四方の長孔3bに、点線矢印
のように下方から並列する電熱線6をそれぞれ挿
通し、各電熱線6をキヤンの内キヤン1bの周面
に沿わせ、それらの屈曲上端部を第4図のように
各周面に設けられた帯板ばね5の凹所に差し込む
とゝもに、基板7上面の止め具7aを底板3の長
孔3b周縁の下面に突出させた弾性挟持具4に係
合させ、かくて加熱部材は第2図のようにキヤン
の内キヤン1bの周面に沿つてそれぞれ簡単に着
脱自在に組付けられる。
Therefore, the heating wires 6 arranged in parallel from below are inserted into the four elongated holes 3b of the bottom plate 3 as shown by the dotted arrows, and the heating wires 6 are placed along the circumferential surface of the inner can 1b, and the bent upper ends of the heating wires 6 are As shown in FIG. 4, the retainers 7a on the upper surface of the board 7 were inserted into the recesses of the strip springs 5 provided on each peripheral surface as shown in FIG. The heating members are engaged with the elastic holding members 4, and thus the heating members can be easily attached and detached along the circumferential surface of the inner can 1b as shown in FIG.

なお、第2図において11はキヤン中にキヤリ
アガスを供給るためのパイプであり、12は水溶
性の放射能を検出するため、キヤン中の水を随時
取出すパイプ、また第3図中の13は電熱線を電
源に接続するためのコードである。
In addition, in Fig. 2, 11 is a pipe for supplying carrier gas during the can, 12 is a pipe for removing water from the can at any time in order to detect water-soluble radioactivity, and 13 in Fig. 3 is a pipe for supplying carrier gas during the can. This is a cord for connecting the heating wire to the power source.

そこで、長期の保管により自己発熱作用の低下
した原子燃料集合体nを内キヤン1b中に収能し
た際には、ジヤケツト室2中にジヤケツトガスを
圧送して該室内の水を適宜に排除して気体層を形
成するとゝもに周囲の電熱線6に通電してこれを
発熱させれば、先ずジヤケツト室2内の温度が上
昇し、これを通じて内キヤン1b中の原子燃料集
合体nがプール水とゝもに加熱され、その組成燃
料棒の内圧が上昇し、内部に生じた核分裂生成物
が破損箇所から漏出することになり、下方から供
給されているキヤリアガスによつて放射線検出器
の方に連行される。
Therefore, when the nuclear fuel assembly n whose self-heating effect has deteriorated due to long-term storage is stored in the inner can 1b, jacket gas is forced into the jacket chamber 2 to properly remove the water in the chamber. When a gas layer is formed and the surrounding heating wires 6 are energized to generate heat, the temperature inside the jacket chamber 2 rises, and through this the nuclear fuel assembly n in the inner can 1b flows into the pool water. As the fuel rods are heated, the internal pressure of the fuel rods increases, and the fission products generated inside leak out from the damaged area, and are transported toward the radiation detector by the carrier gas supplied from below. taken away.

このような一定期間の使用後に、加熱部材の点
検に当たつては、内キヤン1b中から原子燃料集
合体nを取除いてシツピングキヤン1を空にし、
これをクレーン等によつて吊り上げ、地上におい
て底板3に止め部材4,7aを介して結合してい
る基板7を外し、四方の長孔3bから電熱線6を
それぞれ引き抜けばよい。
After such a certain period of use, when inspecting the heating member, remove the nuclear fuel assembly n from the inner can 1b and empty the shipping can 1.
This can be hoisted by a crane or the like, the board 7 connected to the bottom plate 3 via the stoppers 4 and 7a on the ground can be removed, and the heating wires 6 can be pulled out from the four elongated holes 3b, respectively.

そして、絶縁性の良否、破損の有無を点検の
上、必要あれば新しいものと交換の上、再び内キ
ヤン1bに前記のようにして組付ければよい。
Then, after checking the quality of the insulation and the presence or absence of damage, if necessary, replace it with a new one, and then reassemble it to the inner can 1b as described above.

なお、底板3と基板7との止め部材として嵌め
合せ式のものを示したが、これに限らず着脱可能
なものであれば他の手段でもよい。
Although a fitting type member is shown as the fixing member for the bottom plate 3 and the substrate 7, the present invention is not limited to this, and other means may be used as long as it is removable.

以上のようにこの考案によれば、加熱部材の取
付け、取外しが容易にでき、絶縁状態の良否、破
損の有無などの点検ならびに清掃が可能であり、
長期の使用に適し、しかも燃料集合体の発熱効果
を向上させることができる。
As described above, according to this invention, the heating member can be easily installed and removed, and it is possible to inspect the insulation condition and whether there is any damage, as well as to clean it.
It is suitable for long-term use and can improve the heat generation effect of the fuel assembly.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は従来のシツピング装置の概略的な断面
図。第2図はこの考案の実施例の上半部を省略し
た断面図。第3図イは底板の斜視図。同図ロは加
熱部材の斜視図。同図ハは止め部材の対向側面
図。第4図は内キヤンの一部の斜視図。 図中、1……シツピングキヤン、1a……外キ
ヤン、1b……内キヤン、2……ジヤケツト室、
3……底板、3a……中心通孔、3b……長孔、
4……弾性挟持具、5……帯板ばね、6……電熱
線、7……基板、7a……止め具。
FIG. 1 is a schematic cross-sectional view of a conventional shipping device. FIG. 2 is a sectional view with the upper half of the embodiment of this invention omitted. Figure 3A is a perspective view of the bottom plate. Figure B is a perspective view of the heating member. Figure C is a side view of the stopper member. FIG. 4 is a perspective view of a part of the inner can. In the figure, 1... Shipping can, 1a... Outer can, 1b... Inner can, 2... Jacket room,
3... Bottom plate, 3a... Center through hole, 3b... Long hole,
4... Elastic clamping tool, 5... Strip spring, 6... Heating wire, 7... Board, 7a... Stopper.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 外キヤン1aと内キヤン1bおよび両キヤンの
間に形成されたジヤケツト室1cからなり、ジヤ
ケツト室1c内には加熱部材を配設し、内キヤン
1b中に収容した原子燃料集合体nを加熱して核
分裂生成物を漏出させ、破損の有無を検出するよ
うにしたシツピング装置において、底板3の四方
周囲部に、上記内キヤン1bの周囲表面がほぼ長
手方向中央部に位置するようにして所要長さの長
孔3bをそれぞれ設け、上記加熱部材を長孔3b
より若干大きな基板7とこれに所要高さに立設し
た複数の電熱線6とで形成し、該電熱線6を各長
孔3bを介して内キヤン1bの周面上に添設しそ
の上端部を帯板ばね5で支持し、かつ基板7を底
板3の下面に止め部材4,7aにより着脱自在に
取付けたことを特徴とするシツピングキヤン。
It consists of an outer can 1a, an inner can 1b, and a jacket chamber 1c formed between both cans, and a heating member is disposed in the jacket chamber 1c to heat the nuclear fuel assembly n accommodated in the inner can 1b. In a shipping device that leaks nuclear fission products and detects the presence or absence of damage, a required length is provided around the four sides of the bottom plate 3 so that the peripheral surface of the inner can 1b is located approximately at the center in the longitudinal direction. A long hole 3b of the same size is provided, and the heating member is inserted into the long hole 3b.
It is formed by a slightly larger substrate 7 and a plurality of heating wires 6 erected on the substrate at a required height, and the heating wires 6 are attached to the circumferential surface of the inner can 1b through each elongated hole 3b, and the upper end thereof is attached. The shipping can is characterized in that the base plate 7 is supported by a strip spring 5, and the base plate 7 is detachably attached to the lower surface of the bottom plate 3 by means of stoppers 4 and 7a.
JP1983078918U 1983-05-27 1983-05-27 Shipping canister in shipping equipment Granted JPS59185697U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1983078918U JPS59185697U (en) 1983-05-27 1983-05-27 Shipping canister in shipping equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1983078918U JPS59185697U (en) 1983-05-27 1983-05-27 Shipping canister in shipping equipment

Publications (2)

Publication Number Publication Date
JPS59185697U JPS59185697U (en) 1984-12-10
JPH0220718Y2 true JPH0220718Y2 (en) 1990-06-05

Family

ID=30208918

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1983078918U Granted JPS59185697U (en) 1983-05-27 1983-05-27 Shipping canister in shipping equipment

Country Status (1)

Country Link
JP (1) JPS59185697U (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5726688B2 (en) * 2011-09-13 2015-06-03 株式会社東芝 Damaged fuel inspection apparatus and method

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56112503U (en) * 1980-01-30 1981-08-31
JPS6314242Y2 (en) * 1980-02-09 1988-04-21

Also Published As

Publication number Publication date
JPS59185697U (en) 1984-12-10

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