专利快速检索-快速检索全球专利，免费商用专利数据库-IPRDB

1. 发明专利

JPH06347597A SOLIDIFICATION MATERIAL OF RADIOACTIVE WASTE 失效
公开(公告)号：JPH06347597A
公开(公告)日：1994-12-22
申请号：JP13746993
申请日：1993-06-08
申请人： TOSHIBA CERAMICS CO , TOSHIBA CORP
发明人： MATSUO KAZUAKI , TOYOHARA NAOMI , SATO TATSUAKI , NODA TETSUYA , WADA MIKIO
IPC分类号： G21F9/16 , G21F9/30
摘要： PURPOSE:To improve the fluidity of cement paste by adding a specific amount of inorganic builder consisting of special material to cement. CONSTITUTION:If a phosphate glass is added to the cement powder or water for mixing in cement, it works on the surface of cement particles and acts as surfactant. The phosphate glass is expressed as M3-n.Hn.PO4 (0

2. 发明专利

JPS63298197A TREATMENT OF RADIOACTIVE OIL CONTAINING WASTE 失效
公开(公告)号：JPS63298197A
公开(公告)日：1988-12-05
申请号：JP13390487
申请日：1987-05-29
申请人： NIPPON ATOMIC IND GROUP CO , TOSHIBA CORP
发明人： MATSUMOTO KANAME , SEKI HIDEJI , YOSHIKAWA JUN , WADA MIKIO , WAKAMATSU TOSHIFUMI
IPC分类号： G21F9/06 , G21F9/14 , G21F9/16 , G21F9/32
摘要： PURPOSE:To effectively extract oil from oil-containing sludge and drain and enable recovered oil to incinerate by applying carbon tetrachloride as an extract agent which extracts oil from the oil-containing sludge and drain. CONSTITUTION:After oil-containing waste liquid and carbon tetrachloride are mixed and agitated, and oil is extracted in a carbon tetrachloride phase, a sludge phase and a liquid phase are separated each other and the liquid phase is separated to a water phase and an oil-containing carbon tetrachloride phase. Sludge is dried and concentrated, water and tetrachloride are removed from the sludge, which is incinerated into ash. The water phase is dried and concentrated to an evaporative concentrate solid matter as evaporated residue. The oil-containing carbon tetrachloride phase which is heated and evaporated is recovered as carbon tetrachloride and its evaporated residue is incinerated into ash. Said ash and evaporated concentrate are solidified by the use of cement solidification method.

3. 发明专利

JPS62164000A AUTOMATIC MEASURING METHOD OF LEACHING RATE OF SOLIDIFIED BODY 失效
公开(公告)号：JPS62164000A
公开(公告)日：1987-07-20
申请号：JP502786
申请日：1986-01-16
申请人： NIPPON ATOMIC IND GROUP CO , TOSHIBA CORP
发明人： SEKI HIDEJI , WADA MIKIO
IPC分类号： G21F9/34 , G01M3/00 , G01M3/20 , G01T1/167 , G21F9/36

4. 发明专利

JPH08271692A PROCESSING METHOD FOR RADIOACTIVE WASTE LIQUID 失效
公开(公告)号：JPH08271692A
公开(公告)日：1996-10-18
申请号：JP6951795
申请日：1995-03-28
申请人： TOSHIBA CORP
发明人： TOYOHARA NAOMI , MIKURA MICHITAKA , FUJIHATA KENJI , KANEKO MASAAKI , WADA MIKIO , OKANO TOSHIAKI
IPC分类号： G21F9/06 , B01D61/44 , B01J20/18 , C02F1/469 , G21F9/10 , G21F9/12
摘要： PURPOSE: To enable reusing neutral salt in a radioactive material treatment facility by decomposing the neutral salt in waste liquid after removing radioactive nuclides into acid and alkali by electric dialysis and recovering them. CONSTITUTION: Waste liquid containing radioactive nuclides is contained in a pH controlling tank 1, acid is supplied from an acid supply tank 2 and pH of the waste liquid is controlled with a pH meter at 5 or less, and the liquid is transported to a coprecipitation reaction tank 4. To this tank, coprecipitation agents, phosphoric acid ion, lanthanum and alkali, 5 to 7, are supplied. At this moment, the supply amount of alkali is monitored with a pH meter 8 to control the waste liquid after adding the coprecipitation agent at pH3 or higher to let the coprecipitation agent precipitate and let the deposition take in TRU nuclides. The waste liquid containing the deposition is filtered with a filter 9 to make the deposition condensed sludge. The waste liquid removed of TRU nuclides together with the deposition is transported to an ion exchanging tower 11 charged with zeolite to remove Cs and tentatively stored in a reservoir tank 12. Then part of the waste liquid is transported to a waste liquid circulation tank 13 and the salt in the waste liquid is decomposed into acid and alkali with an electric dialyzer 14.

5. 发明专利

JPH05346493A 失效
公开(公告)号：JPH05346493A
公开(公告)日：1993-12-27
申请号：JP15682292
申请日：1992-06-16
申请人： TOSHIBA CORP , TOA GOSEI CHEM IND
发明人： TOYOHARA NAOMI , MIKURA MICHITAKA , WADA MIKIO , AIBA NOBUHIKO , IINUMA TOMOHISA , KATO HIDEKI
IPC分类号： G21F9/12 , B01J41/10
摘要： PURPOSE:To make suppressing resolution of radioactive nuclei for a long time possible by selectively absorbing ion including radioactive iodine and/or technetium with using an absorption processing agent constituted of inorganic ion exchanger. CONSTITUTION:Waste generated from a reactor facility is brought into contact with an absorption treating agent constituted of an inorganic ion exchanger. And ions including radioactive nuclei iodine and/or technetium as structure atoms is selectively absorbed and fixed. As for inorganic ion exchanger, one including at least one of dismuth nitrate hydroxide (III), dismuth nitrate hydroxide (III) expressed with the equation I, complex oxide of aluminum and magnesium expressed with the equation II and zirconium hydrate, or one of them and antimony hydrate combination are used. As the inorganic ion exchanger including the radioactive iodine and technetium obtained in this process is a stable compound, it does not release the nuclei again after the treatment.

6. 发明专利

JPH0215920A WALL SURFACE DECONTAMINATING DEVICE 失效
公开(公告)号：JPH0215920A
公开(公告)日：1990-01-19
申请号：JP16616488
申请日：1988-07-04
申请人： TOKYO ELECTRIC POWER CO , TOHOKU ELECTRIC POWER CO , CHUBU ELECTRIC POWER , HOKURIKU ELECTRIC POWER , CHUGOKU ELECTRIC POWER , JAPAN ATOMIC POWER , TOSHIBA CORP
发明人： AKAHORI FUMINORI , SUDA KENICHI , NARUSE KIYOSHI , OGAMI MASAHARU , NABETA TAKAAKI , SAKAMOTO SEIJI , NAKAYAMA RYOICHI , WADA MIKIO
IPC分类号： B23H5/00 , B23H5/08
摘要： PURPOSE:To enable a large-scale metal construction of being decontaminated effectively within a short period at high efficiency by providing a travelling rail laid on the wall face of an object to be decontaminated, a decontaminating device which executes the electrolytic composite grinding for the wall surface, a controller of the device and a cable processing device used as a relay function. CONSTITUTION:A decontaminating device 7 is mounted as it is able to travel along a travelling rail 6 laid along a wall face. Said device 7 is travelled under the remote control by a controller 5 via a cable processing device 3, while executing the electrolytic composite grinding for the wall face 2. Even if the object to be decontaminated is a large-scale construction, these is no problem and the operation is executed under the remote control by a controller 5 so that exposure of a personnel to radio-active emission may be reduced considerably. The travelling rail 6 itself is able to be moved via the cable processing device 3 so that the specified electrolytic composite grinding may be efficiency executed for the entire wall face 2 and also for the arbitrary portion thereby selectively.

7. 发明专利

JPS63289497A RADIOACTIVE LIQUID WASTE TREATING APPARATUS 失效
公开(公告)号：JPS63289497A
公开(公告)日：1988-11-25
申请号：JP12375787
申请日：1987-05-22
申请人： NIPPON ATOMIC IND GROUP CO , TOSHIBA CORP
发明人： SEKI HIDEJI , SHIRAI TAKAMORI , WADA MIKIO
IPC分类号： G21F9/12 , G21F9/00
摘要： PURPOSE:To suppress generation of a waste while enabling reuse of a radioactive nuclide adsorbent, by connecting a reaction tank, a pump for transferring a liquid treated and a filter for separating the adsorbent in series with a piping. CONSTITUTION:A reaction tank 1, a pump 2 and a filter 3 are arranged in series and the tank 1 is provided with a pipe 4 for introducing a radioactive waste liquor, an agitating device 5 and a pipe 6 for draining and transferring a treated liquid. The radioactive waste liquor is collected to the tank 1 with the pipe 4 and stirred up with the agitating device 5. Under such a condition, a hexacyanoferrate powder is added to the mixture and mixed for a fixed time. The waste liquor thus treated is transferred with the pump 2 to the filter 3 passing through the pipe 6 to separate solid from liquid. The hexacyanoferrate adheres to the surface of the filter of the device 3 to separate and trap a radioactive nuclide therewith and after a treatment thereof at an outlet, water quality is monitored to judge separating and trapping capacity. The hexacyanoferrate with lost separating/trapping capacity is backwashed and returned to the tank 1 for re-use.

8. 发明专利

JPS6338198A METHOD OF SOLIDIFYING AND PROCESSING RADIOACTIVE WASTE 失效
公开(公告)号：JPS6338198A
公开(公告)日：1988-02-18
申请号：JP18167086
申请日：1986-08-01
申请人： NIPPON ATOMIC IND GROUP CO , TOSHIBA CORP
发明人： TOMITA SHUNEI , TOYOHARA NAOMI , WADA MIKIO , NODA TETSUYA
IPC分类号： G21F9/30 , G21F9/00 , G21F9/36

9. 发明专利

JPS62213812A LIQUID TREATMENT DEVICE 失效
公开(公告)号：JPS62213812A
公开(公告)日：1987-09-19
申请号：JP5859886
申请日：1986-03-17
申请人： TOSHIBA CORP , ISHIKAWAJIMA HARIMA HEAVY IND
发明人： WADA MIKIO , NAKAMURA MITSUSHIGE , MIYATA YASUO , ABE TSUNEO
IPC分类号： G21F9/06 , B01D61/10 , B01D61/58 , B01D63/06 , B01D65/02 , B01D65/04 , G21F9/00
摘要： PURPOSE:To remove suspending matters and solutes in one flow with a simple structure and small power by providing a power-rotating brush washing the inner wall in a mechanized way in a membrane tube of a tube-shaped separator. CONSTITUTION:In operating a liquid treatment device equipped with a membrane separator 2 constituted with a membrane module consisting of a plurality of brush-washing membrane tubes, high pressure gas in high pressure gas bomb 9 is stored in a gas supply tank 11 to be supplied to a concentration liquid receiving tank 12 through a pressure regulating valve 13 and pressurizes the inside of said tank 12 with operating pressure of the membrane separator 2. Raw liquid in a raw liquid tank 5 is sent to the membrane separator 2 by operating a high pressure pump 7. Water permeating the semi-permeable membrane in the membrane separator 2 is recovered in a treating water tank 4, and concentrated liquid containing suspending matters and solutes are flowed into the concentrated liquid receiving tank 12. In brush-washing, a continuous washing by rotation of brush is carried out to lower the flow speed in the membrane tube, and the number of membrane tubes in parallel can be reduced as the water passes through the steps of membrane tubes to enable the water to be concentrated in one flow.

10. 发明专利

JPH11109036A ALPHA-RADIOACTIVITY MEASUREMENT METHOD AND DEVICE THEREFOR 失效
公开(公告)号：JPH11109036A
公开(公告)日：1999-04-23
申请号：JP26953897
申请日：1997-10-02
申请人： TOSHIBA CORP
发明人： SANO AKIRA , TAMURA TOSHIYUKI , WADA MIKIO
IPC分类号： G01T1/16
摘要： PROBLEM TO BE SOLVED: To easily and accurately measure the α-radioactivity of an α-contami nated measurement object in a high γ ray field. SOLUTION: A container 2 containing a light element is provided on the side of a measurement sample 1 containing an α radioactive material of a neutron detector 5, the light element inside the container 2 and α rays cause (α, n) reaction, a generated neutron is detected and the α-radioactivity is obtained. Without directly measuring the α rays, the neutron generated by the (α, n) reaction of gas containing the light element filled around and the αrays is measured and the α-radioactivity is obtained. Between the neutron detector and the measurement sample, a γ ray shielding material (lead, iron) is installed. A neutron detection part with an additional function capable of selecting the thickness of the neutron detector 5 (He-3 (5a), BF3, B-10 lined (5B), FC) and the γ ray shielding material (lead, iron and tungsten alloy) corresponding to γ ray intensity is provided.

你已经成功收藏专利！

检索式保存成功!

IPRDB

热门服务

关于我们

友情链接

联系方式