JP2933951B2 - Handling of used core components of fast reactors - Google Patents

Handling of used core components of fast reactors

Info

Publication number
JP2933951B2
JP2933951B2 JP1181854A JP18185489A JP2933951B2 JP 2933951 B2 JP2933951 B2 JP 2933951B2 JP 1181854 A JP1181854 A JP 1181854A JP 18185489 A JP18185489 A JP 18185489A JP 2933951 B2 JP2933951 B2 JP 2933951B2
Authority
JP
Japan
Prior art keywords
fuel
sodium
spent
handling
metal
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 - Fee Related
Application number
JP1181854A
Other languages
Japanese (ja)
Other versions
JPH0346594A (en
Inventor
協二 馬場
範明 高橋
武史 重藤
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CHUGOKU DENRYOKU KK
Kawasaki Motors Ltd
Original Assignee
CHUGOKU DENRYOKU KK
Kawasaki Jukogyo KK
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 by CHUGOKU DENRYOKU KK, Kawasaki Jukogyo KK filed Critical CHUGOKU DENRYOKU KK
Priority to JP1181854A priority Critical patent/JP2933951B2/en
Publication of JPH0346594A publication Critical patent/JPH0346594A/en
Application granted granted Critical
Publication of JP2933951B2 publication Critical patent/JP2933951B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、高速増殖炉の使用済燃料,使用剤制御棒,
使用済遮蔽体等の使用済炉心構成要素を原子炉から搬出
し、運搬,貯蔵する際、付着したナトリウム(冷却材)
を洗浄除去して使用済炉心構成要素をインゴット状態に
して運搬,貯蔵する取扱方法に関する。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a spent fuel for a fast breeder reactor, an agent control rod,
Sodium (coolant) adhering when used core components such as used shields are taken out of the reactor, transported and stored
The present invention relates to a handling method for transporting and storing used core components in an ingot state by washing and removing spent core components.

〔従来の技術〕[Conventional technology]

高速増殖炉の使用済炉心構成要素例えば使用済燃料を
原子炉から搬出する際には、付着したナトリウム(原子
炉冷却材)を洗浄して除去する必要がある。
When a spent core component of the fast breeder reactor, for example, spent fuel is carried out of the reactor, it is necessary to wash and remove the attached sodium (reactor coolant).

通常実用化プラントでは高発熱の使用済燃料を炉心よ
り取り出す際にはナトリウムを満たしたポットに入れた
状態で取扱うことが必要とされているが、このナトリウ
ムを満たしたポットをプールの水中に沈めることはNa−
水反応防止の必要性から不可能で、どうしても使用済燃
料を洗浄して付着しているナトリウムを切る必要があ
る。
Normally, in practical use plants, it is necessary to remove spent fuel with high heat from the core in a pot filled with sodium, but it is necessary to submerge this pot filled with sodium into the pool water The thing is Na-
It is impossible because of the need to prevent water reaction, and it is necessary to clean the spent fuel to remove the attached sodium.

このようなことから、最近、炉心から引抜いた使用済
燃料を水プール内に保管するに先立って、前記炉心から
引抜いた使用済燃料の入っているポットをナトリウムが
満たされている分離槽内に移送し、次に分離槽内にナト
リウムよりも比重が大きく且つ融点が分離槽内のナトリ
ウム温度よりも低くしかもナトリウム及び水プールの水
に対して低反応性の溶融金属を供給し、ナトリウムを除
去して使用済燃料を洗浄し、次いでポット内に前記溶融
金属が入っている状態で水プール内に移送し、水プール
内にて裸の使用済燃料をポットから取り出して水プール
内に貯蔵する高速炉使用済燃料洗浄法がある。先行技術
文献として特開昭63−21597号がある。
For this reason, prior to storing the spent fuel extracted from the core in the water pool, the pot containing the spent fuel extracted from the core is placed in a separation tank filled with sodium. Transfer, then supply molten metal having a higher specific gravity than sodium and a melting point lower than the sodium temperature in the separation tank in the separation tank, and a low reactivity to sodium and water in the water pool to remove sodium. To wash the spent fuel, and then transfer it to the water pool with the molten metal in the pot, and remove the naked spent fuel from the pot in the water pool and store it in the water pool. There is a fast reactor spent fuel cleaning method. As a prior art document, there is JP-A-63-21597.

〔発明が解決しようとする課題〕[Problems to be solved by the invention]

ところで、上記の高速炉使用済燃料洗浄法では、使用
済燃料を裸で水プール内に貯蔵する為、破損燃料の取扱
いは別途缶詰する等の設備が必要である。また水プール
内の水に低融点金属が混入する為水プール浄化系にてこ
れを除去する必要があり、その為の設備も必要となる。
さらに貯蔵設備として水プールを用いている為、プール
水浄化系から比較的多量の放射性廃棄物が発生する。
By the way, in the above-mentioned fast reactor spent fuel cleaning method, since spent fuel is stored naked in a water pool, equipment for handling damaged fuel requires separate canning and the like. In addition, since the low-melting-point metal is mixed into the water in the water pool, it is necessary to remove the low-melting metal in the water pool purification system, and equipment for this is also required.
Furthermore, since a water pool is used as a storage facility, a relatively large amount of radioactive waste is generated from the pool water purification system.

そこで本発明は、破損燃料の取扱設備を必要とせず、
また水プールを使用する場合でも水プール内の水に金属
が混入せず、さらに放射性廃棄物が発生しないように使
用済燃料を始めとする使用済制御棒,使用済遮蔽体等の
高速炉使用済炉心構成要素を洗浄し、運搬,貯蔵する取
扱方法を提供しようとするものである。
Therefore, the present invention does not require equipment for handling damaged fuel,
Also, when using a water pool, use fast reactors such as spent fuel and other used control rods, used shields, etc. so that no metal is mixed into the water in the water pool and no radioactive waste is generated. It is an object of the present invention to provide a handling method for cleaning, transporting and storing used core components.

〔課題を解決するための手段〕[Means for solving the problem]

上記課題を解決するための本発明の高速炉使用済炉心
構成要素取扱方法は、使用済炉心構成要素をナトリウム
入り燃料移送ポットに収納した状態で電子炉から取り出
して分離槽内に入れ、次に分離槽内に高融点でナトリウ
ムよりも比重が大きく且つナトリウムと高温で溶解せず
熱伝達特性に優れた金属を溶融状態で供給し、ナトリウ
ムを上部に浮上させることによりオーバーフローさせて
除去し、次いで燃料移送ポット内の前記高融点金属を固
化させ、然る後インゴット状態で使用済炉心構成要素を
運搬,貯蔵するものである。
In order to solve the above-mentioned problems, the method for handling a spent core component of a fast reactor according to the present invention includes removing the spent core component from an electronic furnace in a state where the spent core component is stored in a fuel transfer pot containing sodium, and placing the spent core component in a separation tank. In the separation tank, a metal having a high melting point and a higher specific gravity than sodium, and not dissolving at high temperature with sodium, is supplied in a molten state with a metal having excellent heat transfer characteristics, and the sodium is floated to the top to overflow and be removed. The refractory metal in the fuel transfer pot is solidified, and then the spent core components are transported and stored in an ingot state.

〔作用〕[Action]

上述の如く本発明の高速炉使用済炉心構成要素取扱方
法は、使用済炉心構成要素を収容したナトリウム入り燃
料移送ポットを分離槽に入れた後、ナトリウムよりも比
重が大きく且つナトリウムと高温で溶解せず熱伝達特性
の優れた高融点の溶融金属を燃料移送ポットに導入して
ナトリウムを上記に浮上させて除去し、溶融金属を固化
して、燃料移送ポット内の使用済炉心構成要素を固化金
属に封入した状態で貯蔵するので、例えば使用済炉心構
成要素が破損燃料の場合は、破損孔が溶融金属によって
封塞される為、健全燃料と同一の取扱いが可能で、特別
な設備は不要である。また燃料移送ポットの外表面を空
気で冷却し乍ら貯蔵すれば、放射性廃棄物が殆んど発生
しない。さらに水との反応性の無い金属を用いることに
よって貯蔵に水プールを使用する場合でも水プールの水
に金属が混入することが無いので、水プール浄化系で金
属を除去する設備は不要であり、また使用済燃料の表面
に残留するナトリウムが水と接触することが無く、反応
が起こらないので、放射性腐食生成物が拡散せず、保
守,補修に伴う被曝も少ない。
As described above, in the method for handling a spent core component of a fast reactor according to the present invention, after placing a fuel transfer pot containing sodium containing a spent core component in a separation tank, the specific gravity is larger than that of sodium and the sodium is melted at a high temperature. Without introducing high melting point molten metal with excellent heat transfer characteristics into the fuel transfer pot, sodium is floated and removed above, and the molten metal is solidified to solidify the spent core components in the fuel transfer pot. Stored in a metal-enclosed state.For example, if the spent core component is damaged fuel, the damaged hole is sealed with molten metal, so it can be handled in the same way as a healthy fuel, and no special equipment is required. It is. Also, if the outer surface of the fuel transfer pot is stored while being cooled with air, almost no radioactive waste is generated. Furthermore, by using a metal that does not react with water, even when a water pool is used for storage, no metal is mixed into the water of the water pool, so there is no need for equipment to remove metals in the water pool purification system. In addition, since the sodium remaining on the surface of the spent fuel does not come into contact with water and does not react, the radioactive corrosion products do not diffuse, and the exposure during maintenance and repair is small.

尚、破損燃料については、インゴット状にした後再び
炉心に戻して、炉心の破損燃料貯蔵場所にて貯蔵する取
扱いも可能である。
It is also possible to handle damaged fuel by returning it to the core after forming it into an ingot and storing it in the damaged fuel storage area of the core.

〔実施例〕〔Example〕

本発明の高速炉使用済炉心構成要素取扱方法の一実施
例を第1図によって説明すると、炉心1で発生した使用
済燃料2は、燃料交換機3と回転プラグ4とにより燃料
交換位置5に運び、予め用意された燃料移送ポット6に
挿入する。この燃料移送ポット6は燃料出入機7により
斜道8を通してArガスセル9内に引上げ、燃料出入機7
のスイング作動と吊り降ろし作動により炉外中継層10内
に一旦収納する。
One embodiment of the method for handling spent core components of a fast reactor according to the present invention will be described with reference to FIG. 1. Spent fuel 2 generated in a reactor core 1 is transported to a refueling position 5 by a fuel exchanger 3 and a rotary plug 4. Into the fuel transfer pot 6 prepared in advance. The fuel transfer pot 6 is pulled up into the Ar gas cell 9 through the ramp 8 by the fuel access device 7,
Is temporarily stored in the relay layer outside the furnace 10 by the swing operation and the hanging-down operation.

その後燃料移送ポット6は燃料移送機11により炉外中
継層10内より引上げて移送し、分離槽12内に吊り降ろ
す。次に分離槽12内に、高融点でナトリウムよりも比重
が大きく、ナトリウム及び水と殆んど反応せず、熱伝達
特性の優れている金属として、例えばAl(融点660℃,
比重約3)又はAl−Si13%合金(シルミンと呼ばれる。
融点570℃,比重約3)等のAl合金、又はカドミウム
(融点321℃,比重約8.6)等を溶融状態で供給し、燃料
移送ポット6内に導入して先に入っていたナトリウムを
上部のオーバーフローホールよりオーバーフローさせて
除去する。次いで燃料移送ポット6内の溶融金属を自然
冷却により固化させて、内部の使用済燃料2を封入す
る。こうしてインゴット状態となった使用済燃料2は燃
料移送ポット6ごとに燃料移送機11により分離槽12内よ
り引上げて移送し、Arガスセル9から隣の空気セル13に
連絡する地下室14の燃料移送用台車15に吊り降ろし、こ
の燃料移送用台車15の走行により空気セル13側に移送
し、空気セル13内の燃料移送機16により燃料移送ポット
6を燃料移送台車15より空気セル13内に引上げて移送
し、地下の貯蔵庫17内に吊り降ろして貯蔵する。
After that, the fuel transfer pot 6 is lifted and transferred from the inside of the relay layer 10 outside the furnace by the fuel transfer device 11, and is suspended in the separation tank 12. Next, in the separation tank 12, as a metal having a high melting point, a higher specific gravity than sodium, hardly reacting with sodium and water, and having excellent heat transfer characteristics, for example, Al (melting point 660 ° C.,
Specific gravity of about 3) or Al-Si 13% alloy (referred to as silumin).
An aluminum alloy having a melting point of 570 ° C. and a specific gravity of about 3) or cadmium (melting point of 321 ° C. and a specific gravity of about 8.6) is supplied in a molten state, and the sodium that has been introduced into the fuel transfer pot 6 is removed from the upper portion. Overflow is removed from the overflow hole. Next, the molten metal in the fuel transfer pot 6 is solidified by natural cooling, and the spent fuel 2 inside is sealed. The spent fuel 2 in the ingot state is lifted and transferred from the separation tank 12 by the fuel transfer device 11 for each fuel transfer pot 6, and is used for fuel transfer in the basement 14 connected to the adjacent air cell 13 from the Ar gas cell 9. The fuel is transported to the air cell 13 side by the traveling of the fuel transfer cart 15, and the fuel transfer pot 6 is pulled up from the fuel transfer cart 15 into the air cell 13 by the fuel transfer machine 16 in the air cell 13. It is transported, suspended and stored in a storage 17 underground.

このように、本発明の高速炉使用済炉心構成要素取扱
方法では、使用済燃料2を収容したナトリウム入り燃料
移送ポット6を分離槽12内に入れ、燃料移送ポット6に
ナトリウムよりも比重が大きくナトリウムと低反応性で
且つ融点の高い金属を溶融状態で導入し、ナトリウムを
オーバーフローさせて除去し、溶融金属を固化して使用
済燃料2をインゴット中に封入した状態で貯蔵するの
で、使用済燃料2が破損している場合、破損孔が溶融金
属によって封塞されて固化する。従って、健全な使用済
燃料2と同一の取扱いができて、特別な設備は不要であ
る。また地下の貯蔵庫17内に貯蔵した際、第1図に示さ
れるようにブロワー18により貯蔵庫17内に空気を吹込ん
で、燃料移送ポット6の外表面を空気で冷却し乍ら貯蔵
すれば、放射性廃棄物が殆んど発生しない。さらに地下
の貯蔵庫17内で貯蔵するのに代えて水との反応性の無い
金属を用いた場合には、第2図に示す水プール19内の貯
蔵ラック20に貯蔵した際、水プール19内の水に金属が混
入することが無いので、水プール浄化系で金属を除去す
る設備は不要であり、また使用済燃料2の表面に残留す
るナトリウムが水と接触することが無く、反応が起こら
ない。
As described above, in the method for handling a spent core component of a fast reactor according to the present invention, the sodium-containing fuel transfer pot 6 containing the spent fuel 2 is placed in the separation tank 12, and the specific gravity of the fuel transfer pot 6 is larger than that of sodium. A metal having low reactivity with sodium and a high melting point is introduced in a molten state, sodium is removed by overflowing, and the molten metal is solidified and stored in a state in which spent fuel 2 is sealed in an ingot. When the fuel 2 is damaged, the damaged hole is sealed by the molten metal and solidified. Therefore, the same handling as the healthy spent fuel 2 can be performed, and no special equipment is required. Further, when the fuel is stored in the underground storage 17, air is blown into the storage 17 by the blower 18 as shown in FIG. 1 and the outer surface of the fuel transfer pot 6 is stored while being cooled by air. Almost no waste is generated. Further, when a metal having no reactivity with water is used instead of being stored in the underground storage 17, when the metal is stored in the storage rack 20 in the water pool 19 shown in FIG. Since no metal is mixed into the water, no equipment for removing the metal in the water pool purification system is required, and the sodium remaining on the surface of the spent fuel 2 does not come into contact with the water, and the reaction occurs. Absent.

尚、上記実施例では使用済燃料の取扱方法について説
明したが、使用済制御棒,使用済遮蔽体の取扱いも同様
に行われるものである。
In the above embodiment, the method of handling the spent fuel has been described. However, the handling of the used control rod and the used shield is also performed in the same manner.

〔発明の効果〕〔The invention's effect〕

以上の説明で判るように本発明の高速炉使用済炉心構
成要素取扱方法によれば、従来必要であった破損燃料の
取扱設備が不要となり、燃料取扱システムの簡素化が可
能である。また使用済炉心構成要素が燃料移送ポット内
でインゴット中に封入された状態で貯蔵されるので、燃
料移送ポットを冷却し乍ら貯蔵することにより放射性廃
棄物が殆んど発生しない。さらに上記燃料移送ポットを
水プール内に貯蔵した場合、金属が水プール内の水に混
入しないので、水プール浄化系に金属除去設備は不要で
あり、しかも万一使用済炉心構成要素の表面にナトリウ
ムが残留付着していてもインゴット中に封じ込められて
いる為直接水プールの水と反応することが無いので、水
プール貯蔵システムを確立できる。
As can be seen from the above description, according to the method of handling a spent core component of a fast reactor according to the present invention, a facility for handling damaged fuel, which has been conventionally required, becomes unnecessary, and the fuel handling system can be simplified. In addition, since the spent core components are stored in the fuel transfer pot in the state of being sealed in the ingot, storing the fuel transfer pot while cooling it causes almost no generation of radioactive waste. Furthermore, when the above-mentioned fuel transfer pot is stored in the water pool, metal does not mix with the water in the water pool. Therefore, no metal removing equipment is required in the water pool purification system, and the surface of the used core component should be used. Even if sodium remains, since it is contained in the ingot and does not directly react with the water in the water pool, a water pool storage system can be established.

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

第1図は本発明の高速炉使用済炉心構成要素取扱方法を
実施する燃料取扱システムを示す図、第2図は第1図の
一部変更例を示す図である。 2……使用済炉心構成要素(使用済燃料) 6……燃料移送ポット、12……分離槽
FIG. 1 is a view showing a fuel handling system for carrying out a method for handling a spent fast reactor core component of the present invention, and FIG. 2 is a view showing a partially modified example of FIG. 2 Spent core components (spent fuel) 6 Fuel transfer pot, 12 Separation tank

───────────────────────────────────────────────────── フロントページの続き (72)発明者 重藤 武史 東京都江東区南砂2丁目4番25号 川崎 重工業株式会社東京設計事務所内 (58)調査した分野(Int.Cl.6,DB名) G21C 19/32 G21C 19/18 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Takeshi Shigeto 2-4-25 Minamisuna, Koto-ku, Tokyo Kawasaki Heavy Industries, Ltd. Tokyo Design Office (58) Field surveyed (Int. Cl. 6 , DB name) G21C 19/32 G21C 19/18

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】使用済炉心構成要素をナトリウム入り燃料
移送ポットに収納した状態で電子炉から取り出して分離
槽内に入れ、次に分離槽内に高融点でナトリウムよりも
比重が大きく且つナトリウムと高温で溶解せず熱伝達特
性に優れた金属を溶融状態で供給し、ナトリウムを上部
に浮上させることによりオーバーフローさせて除去し、
次いで燃料移送ポット内の前記高融点金属を固化させ、
然る後インゴット状態で使用済炉心構成要素を運搬,貯
蔵することを特徴とする高速炉使用済炉心構成要素取扱
方法。
1. A spent core component is taken out of an electronic furnace in a state in which it is stored in a fuel transfer pot containing sodium, and is put into a separation tank. Next, the separation tank has a high melting point, a higher specific gravity than sodium, and The metal which does not melt at high temperature and has excellent heat transfer properties is supplied in a molten state, and the sodium is floated to the top to overflow and remove it.
Next, the high melting point metal in the fuel transfer pot is solidified,
A method for handling spent core components in a fast reactor, comprising transporting and storing the spent core components in an ingot state thereafter.
JP1181854A 1989-07-14 1989-07-14 Handling of used core components of fast reactors Expired - Fee Related JP2933951B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1181854A JP2933951B2 (en) 1989-07-14 1989-07-14 Handling of used core components of fast reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1181854A JP2933951B2 (en) 1989-07-14 1989-07-14 Handling of used core components of fast reactors

Publications (2)

Publication Number Publication Date
JPH0346594A JPH0346594A (en) 1991-02-27
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