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1. 发明专利

JP2002243892A SOLIDIFICATION METHOD FOR RADIOACTIVE ALKALINE WASTE LIQUID 失效
公开(公告)号：JP2002243892A
公开(公告)日：2002-08-28
申请号：JP2001046991
申请日：2001-02-22
申请人： HITACHI LTD , JAPAN NUCLEAR CYCLE DEV INST
发明人： OURA MASATO , FUKAZAWA TETSUO , KAWASAKI HIROSHI , NAKAI SATORU , IMAHORI SHINJI , KONISHI KENSUKE
IPC分类号： G21F9/06 , C04B28/08 , G21F9/16
摘要： PROBLEM TO BE SOLVED: To provide a solidification method for radioactive alkaline waste liquid in which waste liquid of sodium hydroxide converted from metal sodium of fast breeder reactor is solidified with a high density. SOLUTION: The solidification method for radioactive alkaline waste liquid is characterized by that granulated blastfurnace slag is added to the radioactive alkaline waste liquid to solidify.

2. 发明专利

JP2002116288A REACTOR FUEL ROD AND ITS PRODUCTION METHOD 失效
公开(公告)号：JP2002116288A
公开(公告)日：2002-04-19
申请号：JP2000313109
申请日：2000-10-06
申请人： HITACHI LTD , HITACHI ENG CO LTD
发明人： KONUKI NORIHIKO , TAKAHASHI MASANORI , FUKAZAWA TETSUO , SASAHIRA AKIRA
IPC分类号： G21C21/04 , G21C3/62
摘要： PROBLEM TO BE SOLVED: To reduce the process for producing fuel rods with many regions in the axial direction by filling particulate fuel and giving vibration. SOLUTION: In a method for producing fuel rods with different composition in the axial direction in a vibration compaction process, two kinds of compositions of large diameter particles 10-1 for lower part and upper part and large diameter particles 10-2 for middle part are employed, and one kind of composition of small diameter particles 11 is employed. From the bottom of a clad 1, the large diameter particles 10-1, the large diameter particles 10-2 and the small diameter particles 11 are packed in turn. Then, by giving vibration with a vibration generator 4 and making the small diameter particles 11 which permeate lower, fuel regions with uniform density and different compositions in the axial direction can be produced in a single process consisting of packing and vibrating of particle fuel.

3. 发明专利

JP2000199800A REMOVAL METHOD FOR OXIDE FILM ON METAL SURFACE AND ITS DEVICE 失效
公开(公告)号：JP2000199800A
公开(公告)日：2000-07-18
申请号：JP107199
申请日：1999-01-06
申请人： HITACHI LTD , JAPAN NUCLEAR CYCLE DEV INST
发明人： FUKAZAWA TETSUO , TSUCHIYAMA DAISUKE , KATAOKA SHINOBU , YOSHIDA YUTAKA , TAKAHASHI MAKOTO , SAWAHARA SHIGEO
IPC分类号： G21F9/28
摘要： PROBLEM TO BE SOLVED: To realize an effective decontamination method for radioactive materials and hazardous materials. SOLUTION: For the removal method of an oxide film on metal surface having an oxide film, the metal contaminated material 1, on which an oxide film 3 contamination materials such as a radioactive material are adhered or permeated, is immersed in an acid solution 2 to generate cracks 4 in the oxide film 3 in the depth direction. The oxide film 3 is removed by the solution permeated in between the metal parent 5 and the oxide film 3 via the cracks 4 in the oxide film removal method for metal surface.

4. 发明专利

JPH11287890A REPROCESSING METHOD FOR SPENT NUCLEAR FUEL 失效
公开(公告)号：JPH11287890A
公开(公告)日：1999-10-19
申请号：JP9122998
申请日：1998-04-03
申请人： HITACHI LTD
发明人： KAMOSHITA MAMORU , SASAHIRA AKIRA , FUKAZAWA TETSUO
IPC分类号： G21C19/46 , G21F9/06
摘要： PROBLEM TO BE SOLVED: To reprocess spent fast reactor fuel at low cost, by recovering plutonium and uranium from fast reactor fuel in a reprocessing facility for fast reactor and from light water reactor fuel and recovered residual liquid of facility for fast reactor. SOLUTION: Sheared pieces of fast reactor accepted in a reprocessing facility are heated and solved in nitric acid as solution, which is controlled at specific concentration of uranium, plutonium and nitric acid and sent to a multiple step extraction device. The solution is flown from the first step to the final step of the multiple step extractor. Also, mixture solvent of a specific composition is flown from the final step to the first step at a specific flow ratio. By this, the mixture in mixed oxide(MOX) fuel composition can be separated. The solution liquid from the final step of the multiple step extractor is sent to a reprocessing facility for light water reactor. On the other hand, mixed solvent which uranium and plutonium are extracted from is contacted in counter- current with diluted nitric acid water solution containing reducer by using the multiple step extractor. By this, the mixture of totally stripped plutonium and uranium is taken out as diluted nitric acid water solution, denitrated and converted into oxide to be MOX fuel.

5. 发明专利

JPH07260993A RECOVERY METHOD OF NEPTUNIUM 失效
公开(公告)号：JPH07260993A
公开(公告)日：1995-10-13
申请号：JP4679794
申请日：1994-03-17
申请人： HITACHI LTD
发明人： FUKAZAWA TETSUO , KAMOSHITA MAMORU , MIURA NOBORU , NAKAMURA TOMOTAKA
IPC分类号： G21C19/46 , C22B60/00 , G21F9/06
摘要： PURPOSE:To recover Np from a radioactive waste liquid simply, by adding a reducer which can reduce the Fe from the trivalence to the bivalence, in the solution of a spent fuel, so as to reduce the Np from the pentavalence to the quadrivalence. CONSTITUTION:To a reprocessing solution 3 including Np, a reducer 1 of Fe (III), hydroxyamine nitrate, for example, is added and stirred so as to accelerate the reaction, and by leaving it for several hours, the Fe (III) in the solution is reduced to Fe (II), and the Np (V) is reduced to Np (IV Then, by adding an organic solvent extracter 2, tributyl phosphate, for example, to the solution, and stirring and leaving, the Np (IV) is extracted. After that, by separating the organic phase 4 and the water phase 5, the Np is transferred to the organic phase 4, and the majority of fission products are left in the water phase 5, so as to separate the Np and the fission products. This can be applied to the reprocessing waste solution, and the Np can be recovered from the radioactive waste fluid.

6. 发明专利

JPH07148418A METHOD FOR TESTING LEAKAGE IN IODINE FILTER AND APPARATUS FOR THE SAME 失效
公开(公告)号：JPH07148418A
公开(公告)日：1995-06-13
申请号：JP29939593
申请日：1993-11-30
申请人： HITACHI LTD
发明人： FUKAZAWA TETSUO , FUNABASHI KIYOMI , MIURA NOBORU , MIURA HIDEKAZU
IPC分类号： G01M3/00 , B01D53/68 , G21F9/02
摘要： PURPOSE:To detect simply without environmental pollution the leakage in an iodine filter for removing radioactive iodine from offgas from radioactive substance treating facilities. CONSTITUTION:An air introduction apparatus which can change humidity is placed upstream from an iodine filter to be tested; a humidity meter is located downstream from the filter. Dry air from the air introduction apparatus is fed into the iodine filter to remove water from an iodine adsorbent in the filter. Then, air with elevated humidity is fed into the filter. The humidity of air passed through the filter is measured by the humidity meter. The leakage of the iodine filter is judged from the difference in time between the start of humid air supply to the filter and the detection of high humidity by the humidity meter.

7. 发明专利

JPH0631852B2 失效
公开(公告)号：JPH0631852B2
公开(公告)日：1994-04-27
申请号：JP19102889
申请日：1989-07-24
申请人： HITACHI LTD
发明人： FUKAZAWA TETSUO , OOTSUKA MASAHARU , UETAKE NAOTO , OZAWA YOSHIHIRO
IPC分类号： G21F9/16 , G21F9/30 , G21F9/36

8. 发明专利

JPH0691163A METHOD FOR OXIDIZING OR REDUCING DISSOLVED MATERIAL 失效
公开(公告)号：JPH0691163A
公开(公告)日：1994-04-05
申请号：JP561193
申请日：1993-01-18
申请人： HITACHI LTD
发明人： NISHI TAKASHI , KITAMORI TAKEHIKO , FUKAZAWA TETSUO , FUJIMORI HARUO , SASAHIRA AKIRA , OZAWA YOSHIHIRO , SUZUKI KAZUMICHI , YUSA HIDEO , YOSHIDA TOMIO
IPC分类号： B01J19/12 , B01J23/40 , B01J35/02 , C02F1/30 , C02F1/70 , C02F1/72 , G21F9/06
摘要： PURPOSE:To drastically improve the efficiency of photo-oxidation or photoreduction by irradiating the granular semiconductor photocatalyst in the aq. nitric acid in which the material contained in the spent nuclear fuel is dis solved with a electromagnetic wave having an energy sufficient to excite the catalyst. CONSTITUTION:Aq. nitric acid, in which the material contained in the spent nuclear fuel is dissolved, is used as a processing soln. 7, a granular semiconductor photocatalyst 8 is used as the semiconductor photocatalyst, and the dissolved material is oxidized or reduced in the presence of a water-soluble electron acceptor or an electron donor. The excitation light 4 emitted from a light source 1 is passed through a glass filter 2 and deflected by a reflecting mirror 3 to irradiate the processing soln. 7 in a reaction vessel 5. The processing soln. 7 contains the fine particle of the photocatalyst 8 which is uniformly dispersed by a stirrer 11. The oxidation or reduction efficiency of the dissolved material is drastically enhanced.

9. 发明专利

JPH05188197A RECOVERING DEVICE FOR NEPTUNIUM FROM ACIDIC SOLUTION 失效
公开(公告)号：JPH05188197A
公开(公告)日：1993-07-30
申请号：JP545992
申请日：1992-01-16
申请人： HITACHI LTD
发明人： NAKAMURA TOMOTAKA , FUKAZAWA TETSUO , YONEDA KENICHIRO
IPC分类号： G21F9/12
摘要： PURPOSE:To recover neptunium from a solution with a simple system and in a short time, because the adjustment of valence to quadrivalent making separation easy and the separation with a scavenger can be continuously carried out in the same device. CONSTITUTION:An acidic solution containing neptunium is continuously supplied from a solution inlet 5 of a column 2 divided into a plurality of steps by glass filters 1 and of which a platinum group catalyst 3 and a scavenger 4 for neptunium are alternately filled in the respective steps. Neptunium is valence-adjusted to quadrivalent by contact with the catalyst 3, and separated from the solution with the scavenger 4. The solution from which neptium is separated is sent from the solution outlet 6 to the other processing facilities, etc. On the other hand, the scavenger 4 of which the separation capacity is reduced, is recovered from outlets 7 for recovering the scavenger, and simultaneously a new scavenger is supplied from inlets 8 for scavenger.

10. 发明专利

JPH0531120B2 失效
公开(公告)号：JPH0531120B2
公开(公告)日：1993-05-11
申请号：JP3796182
申请日：1982-03-12
申请人： HITACHI LTD
发明人： KAWAMURA FUMIO , FUKAZAWA TETSUO , UETAKE NAOTO , FUNABASHI KYOMI
IPC分类号： G21F9/00 , G21F9/16 , G21F9/30

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