JP4178237B2 - Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste - Google Patents
Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste Download PDFInfo
- Publication number
- JP4178237B2 JP4178237B2 JP2003323837A JP2003323837A JP4178237B2 JP 4178237 B2 JP4178237 B2 JP 4178237B2 JP 2003323837 A JP2003323837 A JP 2003323837A JP 2003323837 A JP2003323837 A JP 2003323837A JP 4178237 B2 JP4178237 B2 JP 4178237B2
- Authority
- JP
- Japan
- Prior art keywords
- uranium
- allophane
- radioactive waste
- waste liquid
- recovering
- 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 - Lifetime
Links
- 229910052770 Uranium Inorganic materials 0.000 title claims description 67
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 67
- 238000000034 method Methods 0.000 title claims description 14
- 239000002901 radioactive waste Substances 0.000 title claims description 14
- 239000007788 liquid Substances 0.000 title claims description 13
- 239000002699 waste material Substances 0.000 title claims description 12
- 229910001583 allophane Inorganic materials 0.000 claims description 18
- 239000000463 material Substances 0.000 claims description 11
- 238000009375 geological disposal Methods 0.000 claims description 7
- 239000003929 acidic solution Substances 0.000 claims description 4
- 230000015572 biosynthetic process Effects 0.000 claims description 4
- 238000009792 diffusion process Methods 0.000 claims description 4
- 230000001934 delay Effects 0.000 claims description 3
- 239000003463 adsorbent Substances 0.000 description 7
- 239000000243 solution Substances 0.000 description 7
- 238000001179 sorption measurement Methods 0.000 description 6
- 229910000278 bentonite Inorganic materials 0.000 description 5
- 239000000440 bentonite Substances 0.000 description 5
- SVPXDRXYRYOSEX-UHFFFAOYSA-N bentoquatam Chemical compound O.O=[Si]=O.O=[Al]O[Al]=O SVPXDRXYRYOSEX-UHFFFAOYSA-N 0.000 description 5
- 239000007864 aqueous solution Substances 0.000 description 3
- 230000007613 environmental effect Effects 0.000 description 3
- 239000002927 high level radioactive waste Substances 0.000 description 3
- 238000000746 purification Methods 0.000 description 3
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 3
- TUSDEZXZIZRFGC-UHFFFAOYSA-N 1-O-galloyl-3,6-(R)-HHDP-beta-D-glucose Natural products OC1C(O2)COC(=O)C3=CC(O)=C(O)C(O)=C3C3=C(O)C(O)=C(O)C=C3C(=O)OC1C(O)C2OC(=O)C1=CC(O)=C(O)C(O)=C1 TUSDEZXZIZRFGC-UHFFFAOYSA-N 0.000 description 2
- 239000001263 FEMA 3042 Substances 0.000 description 2
- PXGOKWXKJXAPGV-UHFFFAOYSA-N Fluorine Chemical compound FF PXGOKWXKJXAPGV-UHFFFAOYSA-N 0.000 description 2
- LRBQNJMCXXYXIU-PPKXGCFTSA-N Penta-digallate-beta-D-glucose Natural products OC1=C(O)C(O)=CC(C(=O)OC=2C(=C(O)C=C(C=2)C(=O)OC[C@@H]2[C@H]([C@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)[C@@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)[C@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)O2)OC(=O)C=2C=C(OC(=O)C=3C=C(O)C(O)=C(O)C=3)C(O)=C(O)C=2)O)=C1 LRBQNJMCXXYXIU-PPKXGCFTSA-N 0.000 description 2
- YKTSYUJCYHOUJP-UHFFFAOYSA-N [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] Chemical compound [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] YKTSYUJCYHOUJP-UHFFFAOYSA-N 0.000 description 2
- GUJOJGAPFQRJSV-UHFFFAOYSA-N dialuminum;dioxosilane;oxygen(2-);hydrate Chemical compound O.[O-2].[O-2].[O-2].[Al+3].[Al+3].O=[Si]=O.O=[Si]=O.O=[Si]=O.O=[Si]=O GUJOJGAPFQRJSV-UHFFFAOYSA-N 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000011737 fluorine Substances 0.000 description 2
- 229910052731 fluorine Inorganic materials 0.000 description 2
- 229910052901 montmorillonite Inorganic materials 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000009376 nuclear reprocessing Methods 0.000 description 2
- 229920002635 polyurethane Polymers 0.000 description 2
- 239000004814 polyurethane Substances 0.000 description 2
- 238000012958 reprocessing Methods 0.000 description 2
- LRBQNJMCXXYXIU-NRMVVENXSA-N tannic acid Chemical compound OC1=C(O)C(O)=CC(C(=O)OC=2C(=C(O)C=C(C=2)C(=O)OC[C@@H]2[C@H]([C@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)[C@@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)[C@@H](OC(=O)C=3C=C(OC(=O)C=4C=C(O)C(O)=C(O)C=4)C(O)=C(O)C=3)O2)OC(=O)C=2C=C(OC(=O)C=3C=C(O)C(O)=C(O)C=3)C(O)=C(O)C=2)O)=C1 LRBQNJMCXXYXIU-NRMVVENXSA-N 0.000 description 2
- 229940033123 tannic acid Drugs 0.000 description 2
- 235000015523 tannic acid Nutrition 0.000 description 2
- 229920002258 tannic acid Polymers 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000002378 acidificating effect Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- 230000003100 immobilizing effect Effects 0.000 description 1
- 229910052500 inorganic mineral Inorganic materials 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 239000011707 mineral Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
- 230000002522 swelling effect Effects 0.000 description 1
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical compound F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 description 1
Description
本発明は、放射性廃棄物等に含まれるウランを吸着するウラン吸着剤及び地層中へのウランの拡散を防止あるいは遅延させる放射性廃棄物の処理方法、及びそれらを用いてウランを回収する方法及びウランを固化処理する方法に関する。 The present invention relates to a uranium adsorbent that adsorbs uranium contained in radioactive waste and the like, a method for treating radioactive waste that prevents or delays diffusion of uranium into the formation, and a method and uranium for recovering uranium using them. It relates to a method of solidifying.
近年、核燃料再処理工程等から排出されるウラン含有溶液中のウランを回収するにあたっては、フッ素を用いて六フッ化ウランを生成させる方法（例えば、特許文献１、２参照）、タンニン酸またはポリウレタン系材料を用いてウランを吸着し回収する方法（例えば、特許文献３、４参照）などが提案されている。
ところで、従来の方法は、高濃度なウラン溶液に加えて強酸性条件下におけるウラン回収を目的とするものであるため、フッ素、タンニン酸あるいはポリウレタン系材料という人工的に合成されたもの、または固体として安定に存在しない材料による吸着である。しかし、ウラン鉱山や排出されたウラン含有廃液からウランを回収するには、その処分システムを考慮した場合、環境浄化等の観点から長期に亘って安定に存在するものを用いることが望ましい。
In recent years, in recovering uranium in a uranium-containing solution discharged from a nuclear fuel reprocessing step or the like, a method of generating uranium hexafluoride using fluorine (see, for example, Patent Documents 1 and 2), tannic acid or polyurethane A method of adsorbing and recovering uranium using a system material (see, for example, Patent Documents 3 and 4) has been proposed.
By the way, the conventional method is intended to recover uranium under strongly acidic conditions in addition to a high-concentration uranium solution. Therefore, an artificially synthesized material such as fluorine, tannic acid or polyurethane-based material, or a solid Adsorption by a material that does not exist stably. However, in order to recover uranium from a uranium mine or discharged uranium-containing waste liquid, it is desirable to use a uranium that exists stably over a long period of time from the viewpoint of environmental purification and the like when considering its disposal system.
一方、高レベル放射性廃棄物処理において、緩衝材としてモンモリロナイトを主成分とするベントナイトを用いる方法（例えば、特許文献５参照）が提案されているが、ベントナイトは主にその膨潤性を効率的に利用したシール性を有することを特徴とするものであり、またベントナイト中に含まれるモンモリロナイトによりある程度のウラン吸着効果も有している。
しかし、ベントナイトは、多量の水を含んで膨潤してしまった場合、あるいはＮａからＣａにイオン交換が進行して膨潤機能が低下した場合、また水との反応により２次鉱物が生成した場合と、ウラン吸着効果が低下する可能性がいくつか想定されている。そこで１５０℃以下でも安定であり、アルカリ領域においてもウラン吸着能を有する材料が求められている。
On the other hand, in high-level radioactive waste treatment, a method using bentonite mainly composed of montmorillonite as a buffer material has been proposed (for example, see Patent Document 5). Bentonite mainly uses its swelling property efficiently. In addition, the montmorillonite contained in the bentonite has a certain degree of uranium adsorption effect.
However, bentonite contains a large amount of water and swells, or when ion exchange proceeds from Na to Ca and the swelling function decreases, and when secondary minerals are produced by reaction with water. There are several possibilities that the uranium adsorption effect is reduced. Therefore, a material that is stable at 150 ° C. or lower and has a uranium adsorption ability even in an alkaline region is demanded.
本発明は、従来の技術における上記した実状に鑑みてなされたものである。すなわち、本発明の目的は、天然にも存在する材料を用いて放射性廃棄物中のウランを長期に亘り安定して吸着し、環境浄化に寄与するウラン吸着能に優れたウラン吸着剤を提供することにある。
また、本発明の他の目的は、天然に存在する材料を用いて、ウラン含有液中のウランを効率的に回収する方法を提供することにある。さらに、本発明の他の目的は、放射性廃棄物の地層処分において地層中へのウランの拡散を防止あるいは遅延させる放射性廃棄物の処理方法を提供することにある。
This invention is made | formed in view of the above-mentioned actual condition in a prior art. That is, an object of the present invention is to provide a uranium adsorbent having excellent uranium adsorbing ability that stably adsorbs uranium in radioactive waste over a long period of time using materials that exist in nature and contributes to environmental purification. There is.
Another object of the present invention is to provide a method for efficiently recovering uranium in a uranium-containing liquid using a naturally occurring material. It is another object of the present invention to provide a method for treating radioactive waste that prevents or delays the diffusion of uranium into the formation during geological disposal of radioactive waste.
本発明は、ウラン含有廃液中のウランを吸着するアロフェンからなるウラン吸着剤である。
また、本発明は、ウラン含有廃液の酸性溶液にアロフェンを添加してウランを吸着させるウラン含有廃液中のウラン回収方法である。
さらに、本発明は、放射性廃棄物処理における緩衝材にアロフェンを添加して、ウランを吸着させ、地層中へのウランの拡散を防止あるいは遅延させる放射性廃棄物の処理法である。
The present invention is a uranium adsorbent comprising allophane that adsorbs uranium in a uranium-containing waste liquid.
The present invention is also a method for recovering uranium in a uranium-containing waste liquid by adding allophane to an acidic solution of the uranium-containing waste liquid to adsorb uranium.
Furthermore, the present invention is a method for treating radioactive waste in which allophane is added to a buffer material in radioactive waste treatment to adsorb uranium and prevent or delay the diffusion of uranium into the formation .
本発明によれば、ウラン鉱山や核再処理施設などから排出されるウラン含有廃液からウランを安全にかつ容易に高率で回収できるウラン回収剤を提供するものである。
また、本発明の吸着剤は、高濃度のウランを含む放射性廃棄物を地層処分する際、ウランを長期に亘り安定して吸着し保持するから、放射性廃棄物処理の安全性を促進させることができる。
The present invention provides a uranium recovery agent that can recover uranium safely and easily at a high rate from uranium-containing waste liquid discharged from uranium mines, nuclear reprocessing facilities, and the like.
In addition, the adsorbent of the present invention can adsorb and hold uranium stably for a long time when geological disposal of radioactive waste containing high concentration of uranium, which can promote the safety of radioactive waste treatment. it can.
本発明は、アロフェンからなるウラン吸着剤であって、ウランを産出するウラン鉱山から排出されるウラン含有廃液の酸性溶液中のウラン、及び原子力発電所や核燃料再処理施設等から排出されるウラン含有廃液の酸性溶液中のウランを吸着して回収するために、また、高濃度放射性廃棄物を地層処分する際に、長期に亘り安定してウランを固定化させるために用いられる。 The present invention is a uranium adsorbent composed of allophane, containing uranium in an acidic solution of a uranium-containing waste liquid discharged from a uranium mine producing uranium, and containing uranium discharged from a nuclear power plant, a nuclear fuel reprocessing facility, etc. It is used for adsorbing and recovering uranium in an acidic solution of waste liquid, and for immobilizing uranium stably over a long period of time when geological disposal of high-concentration radioactive waste.
本発明において、ウランの吸着に用いられるアロフェンは、天然にも存在するアルミニウムケイ酸塩であって、Si-O-Al結合を有する非晶質なアルミニウムケイ酸塩である。このアロフェンは、中空球状形態からなり、主に火山灰の風化土壌中に産出するものである。このアロフェンの使用量は、ウランを含む廃液（ウラン濃度０．０１％溶液）に対して、０．０１〜５％の範囲であり、好ましくは０．１〜０．５％である。 In the present invention, allophane used for adsorption of uranium is a naturally occurring aluminum silicate, which is an amorphous aluminum silicate having a Si- O-Al bond . Allophane This consists of a hollow spherical form, is intended primarily to yield to weathering in the soil of volcanic ash. The amount of allophane used is in the range of 0.01 to 5%, preferably 0.1 to 0.5%, with respect to the waste liquid containing uranium (uranium concentration 0.01% solution).
そのアロフェンは、ウラン吸着能に優れており、低温領域においては長期に亘り変質することがないことから、ウラン吸着剤として有用であり、特に、高レベル放射性廃棄物処理の地層処分において、放射性廃棄物の外側を覆うベントナイトを含む緩衝剤のウラン吸着能を高めるために好適であり、地層処分においてより安全なシステムを構築することができる。 The allophane has an excellent ability to adsorb uranium, and it is useful as a uranium adsorbent because it does not change for a long time in the low temperature region. Especially in the geological disposal of high-level radioactive waste treatment, It is suitable for enhancing the uranium adsorption capacity of a buffer containing bentonite covering the outside of the object, and a safer system can be constructed in geological disposal.
実施例
以下、本発明を実施例によりさらに具体的に説明するが、本発明はこれらの実施例によって何ら限定されるものではない。
Examples Hereinafter, the present invention will be described more specifically with reference to examples. However, the present invention is not limited to these examples.
ｐＨ３．５に調整した０．５ｍＭ硝酸ウラニル水溶液に、０．５ｇのアロフェンを入れ、４８時間常温で振盪させた。反応前の溶液と反応後の溶液との濃度の差からアロフェンの吸着量を求めたところ、アロフェン１ｇあたりのウラン吸着量は８．６４ｍｇであった。また、ｐＨ５．０に調整した０．５ｍＭ硝酸ウラニル水溶液に０．５ｇのアロフェンを入れて反応させた場合には、アロフェン１ｇあたり１６．７０ｍｇのウラン吸着量であった。 0.5 g of allophane was placed in a 0.5 mM uranyl nitrate aqueous solution adjusted to pH 3.5 and shaken at room temperature for 48 hours. When the amount of allophane adsorbed was determined from the difference in concentration between the solution before the reaction and the solution after the reaction, the amount of uranium adsorbed per 1 g of allophane was 8.64 mg. Further, when 0.5 g of allophane was added to a 0.5 mM uranyl nitrate aqueous solution adjusted to pH 5.0 and reacted, the amount of uranium adsorbed was 16.70 mg per 1 g of allophane.
ｐＨ１０．５に調整した０．５ｍＭ硝酸ウラニル水溶液に、０．５ｇのアロフェンを入れ、４８時間常温で振盪させた。反応前の溶液と反応後の溶液との濃度の差からアロフェンの吸着量を求めたところ、アロフェン１ｇあたりのウラン吸着量は１７．０９ｍｇであった。 0.5 g of allophane was placed in a 0.5 mM uranyl nitrate aqueous solution adjusted to pH 10.5 and shaken at room temperature for 48 hours. When the amount of allophane adsorbed was determined from the difference in concentration between the solution before the reaction and the solution after the reaction, the amount of uranium adsorbed per 1 g of allophane was 17.09 mg.
本発明は、ウランを産出する鉱山及び核再処理施設などから排出されるウラン含有廃液中のウランを安全にかつ簡易に吸着し、回収するウラン吸着剤であって、環境浄化に大きく貢献できるものであり、また、高レベル廃棄物の地層処分における緩衝材の性能向上に寄与し、放射性廃棄物処理に有用である。
The present invention is a uranium adsorbent that safely and easily adsorbs and recovers uranium in uranium-containing waste liquid discharged from mines and nuclear reprocessing facilities that produce uranium, and can greatly contribute to environmental purification. Moreover, it contributes to the improvement of the performance of the buffer material in the geological disposal of high-level waste, and is useful for radioactive waste treatment.
Claims (2)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2003323837A JP4178237B2 (en) | 2003-09-17 | 2003-09-17 | Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2003323837A JP4178237B2 (en) | 2003-09-17 | 2003-09-17 | Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JP2005091116A JP2005091116A (en) | 2005-04-07 |
| JP4178237B2 true JP4178237B2 (en) | 2008-11-12 |
Family
ID=34454761
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2003323837A Expired - Lifetime JP4178237B2 (en) | 2003-09-17 | 2003-09-17 | Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP4178237B2 (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2009157501A1 (en) * | 2008-06-27 | 2009-12-30 | 竹本 淳 | Method of detoxifying harmful substance, waste disposal site, and paved road |
| WO2011152909A2 (en) | 2010-03-09 | 2011-12-08 | Kurion, Inc. | Isotope-specific separation and vitrification using ion-specific media |
| JP2013061195A (en) * | 2011-09-12 | 2013-04-04 | Toda Kogyo Corp | Method and apparatus for purifying contaminated water containing radioactive substance |
| JP5843060B2 (en) * | 2011-09-12 | 2016-01-13 | 戸田工業株式会社 | Ion adsorbent and method for producing the same |
| JP2013174533A (en) * | 2012-02-27 | 2013-09-05 | Nippon Steel & Sumikin Eco-Tech Corp | Method for reducing amount of spatial radiation inside site and building structure contaminated with radiation substance |
| CA2866198C (en) | 2012-03-26 | 2019-05-21 | Kurion, Inc. | Selective regeneration of isotope-specific media resins in systems for separation of radioactive isotopes from liquid waste materials |
-
2003
- 2003-09-17 JP JP2003323837A patent/JP4178237B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JP2005091116A (en) | 2005-04-07 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Haefner | Methods of gas phase capture of iodine from fuel reprocessing off-gas: a literature survey | |
| Rosenberg et al. | Uranium remediation by ion exchange and sorption methods: a critical review | |
| US4087375A (en) | Method for treating radioactive waste water | |
| KR20150105392A (en) | Strontium and cesium specific ion-exchange media | |
| JP2013088391A (en) | Processing method of material containing radioactive cesium and radioactive strontium | |
| JP4178237B2 (en) | Method for recovering uranium in uranium-containing waste liquid and method for treating radioactive waste | |
| Nayak et al. | Biosorption of toxic, heavy, no-carrier-added radionuclides by calcium alginate beads | |
| JP2013127437A (en) | Method and device for treating radioactive cesium-containing substance | |
| US4808318A (en) | Process for cesium decontamination and immobilization | |
| Kulyukhin et al. | Chemistry of radioactive iodine in aqueous media: Basic and applied aspects | |
| JP5881482B2 (en) | Method and apparatus for treating radioactive cesium contaminants | |
| JP2013120102A (en) | Method for decontaminating soil contaminated with radioactive material | |
| KR100764904B1 (en) | METHOD FOR RECOVERING OF THE SPENT ION EXCHANGE MATERIALS SELECTIVE FOR THE Cs AND Sr ION SORPTION | |
| Cai et al. | Power production waste | |
| JP5610412B2 (en) | Method for insolubilizing water-soluble radioactive cesium, insolubilizing agent used in this method, and hardened cement and concrete obtained by this method | |
| WO2021107811A1 (en) | Method for processing liquid tritium-containing radioactive waste | |
| JPH07270597A (en) | Buffer material or back-filling material for geological disposal of radioactive waste | |
| JP2008304280A (en) | Actinoid adsorption material and method for treating radioactive waste liquid | |
| JP3058705B2 (en) | Radioactive waste treatment method and pretreatment equipment | |
| KR20060023206A (en) | Method for fixing of carbon dioxide | |
| JP6213710B2 (en) | Purification of soil and wastewater contaminated with hazardous substances | |
| EP0456382B1 (en) | A method for the removal of radioisotope cations from an aqueous environment using modified clinoptilolite | |
| JPS62176913A (en) | Process for separation and recovery of cesium from treating liquid containing sodium salt | |
| JPH0659391B2 (en) | Lithium isotope separation agent and method for separating lithium isotope using the same | |
| Nascimento et al. | Removal of radionuclides from acid mine waters by retention on adsorbing materials |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A621 | Written request for application examination |
Free format text: JAPANESE INTERMEDIATE CODE: A621 Effective date: 20050315 |
|
| A977 | Report on retrieval |
Free format text: JAPANESE INTERMEDIATE CODE: A971007 Effective date: 20060922 |
|
| A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20071113 |
|
| A521 | Request for written amendment filed |
Free format text: JAPANESE INTERMEDIATE CODE: A523 Effective date: 20080115 |
|
| A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20080325 |
|
| A521 | Request for written amendment filed |
Free format text: JAPANESE INTERMEDIATE CODE: A523 Effective date: 20080526 |
|
| TRDD | Decision of grant or rejection written | ||
| A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 20080729 |
|
| A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 |
|
| R150 | Certificate of patent or registration of utility model |
Ref document number: 4178237 Country of ref document: JP Free format text: JAPANESE INTERMEDIATE CODE: R150 Free format text: JAPANESE INTERMEDIATE CODE: R150 |
|
| S533 | Written request for registration of change of name |
Free format text: JAPANESE INTERMEDIATE CODE: R313533 |
|
| R350 | Written notification of registration of transfer |
Free format text: JAPANESE INTERMEDIATE CODE: R350 |
|
| EXPY | Cancellation because of completion of term |