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31. 发明专利

JP2000075087A Processing method for radioactive waste and its processing device 有权
标题翻译：放射性废物处理方法及其处理装置
公开(公告)号：JP2000075087A
公开(公告)日：2000-03-14
申请号：JP24928298
申请日：1998-09-03
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： SASAHIRA AKIRA , YOKOI HIROTO , FUKAZAWA TETSUO , NISHI TAKASHI , KAMOSHITA MAMORU , NOSHITA KENJI
IPC分类号： G21C19/46 , G21F9/06
CPC分类号： Y02W30/883
摘要： PROBLEM TO BE SOLVED: To provide a processing method for radioactive waste using electrolyte containing Ag2+ which can reduce the amount of spent ion exchanger material. SOLUTION: By contacting nitric acid solution containing Ag2+ with U, Pu and Np having adhered to a filter in a reaction tank 1, these elements are solved in the nitric acid solution by the Ag2+ effects. In a cathode chamber 7 wherein a cathode 9 of the main electrolysis tank 2 is placed, the Ag2+ in nitric acid solution containing the solved elements is reduced to Ag+. These elements are removed from the nitric acid solution exhausted from the cathode chamber 7 by the ion exchanger material in an ion exchanger tower 3. In an anode chamber 6 wherein an anode 8 of the main electrolysis tank 2 is placed, the Ag+ contained in the nitric acid solution is oxidized to Ag2+. As removal amount of Ag2+ by the ion exchanger material can be drastically reduced, the life of ion exchanger material is extended and thus the generation amount of spent ion exchanger material is drastically reduced.
摘要翻译：要解决的问题：提供使用含有Ag2 +的电解质的放射性废物的处理方法，其可以减少废离子交换剂材料的量。解决方案：通过将含有Ag2 +的硝酸溶液与附着在反应槽1中的过滤器的U，Pu和Np接触，这些元素通过Ag2 +效应溶解在硝酸溶液中。在其中放置主电解槽2的阴极9的阴极室7中，将含有溶解元素的硝酸溶液中的Ag 2 +还原为Ag +。这些元素从离子交换塔3中的离子交换剂材料从阴极室7排出的硝酸溶液中除去。在其中放置主电解槽2的阳极8的阳极室6中，包含在硝酸溶液被氧化成Ag2 +。由于离子交换剂材料的Ag 2+的去除量可以大大降低，离子交换剂材料的寿命延长，因此废离子交换剂材料的产生量急剧降低。

32. 发明专利

JPH10186089A PROCESSING METHOD FOR FUEL REPROCESSING WASTE 失效
公开(公告)号：JPH10186089A
公开(公告)日：1998-07-14
申请号：JP34093896
申请日：1996-12-20
申请人： HITACHI LTD
发明人： HIROSE YASUO , SUZUOKI AKIRA , FUKAZAWA TETSUO
IPC分类号： G21F9/06
摘要： PROBLEM TO BE SOLVED: To reduce the generated quantity of a solidified body by synthesizing sodium zirconiumphosphate NaZr2 P3 O12 (NZP) using zirconium as the major composition element and having a three-dimensional crystal structure belonging to a space group indicated by a specific symbol. SOLUTION: NZP using zirconium as the major composition element and having a three-dimensional crystal structure belonging to a space group indicated by a symbol of R-3C is synthesized. Spent fuel rods are sheared and uranium plutonium is dissolved in a nitric acid solution in the shearing/eluting process 1. The uranium plutonium is recovered in the purex solvent process 2, and it is refined in the refining process 3. Assembly metal wastes are oxidized in the air in the heating/oxidizing process 4, and zirconium oxide powder is obtained. NZP powder is obtained in the NZP molding process 5, and a green compact is formed and sintered in the sintering/solidifying process 11. A sintered body of NZP is sealed in a vessel in a vessel sealing process 12, and the vessel is decontaminated on the surface in the decontaminating process 13 and is disposed as wastes.

33. 发明专利

JPH09318791A REPROCESSING METHOD FOR SPENT FUEL 失效
公开(公告)号：JPH09318791A
公开(公告)日：1997-12-12
申请号：JP13611296
申请日：1996-05-30
申请人： HITACHI LTD
发明人： KAMOSHITA MAMORU , FUKAZAWA TETSUO , SASAHIRA AKIRA
IPC分类号： G21C19/46 , B01D15/04 , C01G43/00 , C01G56/00
摘要： PROBLEM TO BE SOLVED: To provide a reprocessing method of spent fuel in which plutonium is extracted prior to uranium an also a method in which neptunium is recovered together with plutonium to make MOX fuel. SOLUTION: In the present reprocessing method, a complex former 16 is added to spent fuel 1 to make tetravalent plutonium exist as a cation complex and separate with a cation exchanging method, which leads to reducing extraction steps necessary for the total recovery of plutonium in co-decontamination process in reprocessing and making the co-decontamination possible with the element composition close to the plutonium/uranium ratio necessary for MOX fuel 9. The complex former 16 is worked also on neptunium to make plutonium and neptunium exist in tetravalent state as cation complexes which are separated with a cation exchanging method. Neptunium is recovered together with plutonium into MOX fuel, which are isolated in the fuel cycle.

34. 发明专利

JPH09171096A METHOD AND DEVICE FOR TREATING RADIOACTIVE WASTE 失效
公开(公告)号：JPH09171096A
公开(公告)日：1997-06-30
申请号：JP33149895
申请日：1995-12-20
申请人： HITACHI LTD
发明人： NISHI TAKASHI , NOSHITA KENJI , MATSUDA MASAMI , FUKAZAWA TETSUO , IZUMIDA TATSUO
IPC分类号： G21F9/10 , G21F9/02 , G21F9/16
摘要： PROBLEM TO BE SOLVED: To prevent radioactive iodine from volatilizing and improve volume reduction and crack-resistance by separating radioactive iodine in the form of silver iodide from radioactive wasters, mixing into it vitrifying materials consisting of three components of phosphorous, silver and oxygen or four components of those three elements and iodine, heating the mixture to melt it and cooling it to solidify it. SOLUTION: If wasters are loaded into a heating furnace 1 and heated while feeding the air, iodine in the wasters vaporizes in the form of silver iodide. The generated gas is introduced to a cooling tower 2 to cool it, is precipitated on a wall face and is scraped to pulverize it. After pouring the powder of silver iodide into a melting furnace 5 together with vitrifying materials and stirring it there, vitrified solids are obtained by air-cooling spontaneously the melted liquid. In this process, silver phosphate is the most suitable as a vitrified material, but silver iodide may be added further to the vitrifying materials beforehand. Consequently, the yield of vitrified solids which should be managed as waters containing iodine can be substantially reduced, cracks scarcely occur and the low solubility of the vitrified solids makes it possible to improve the performance for confining radioactive iodine.

35. 发明专利

JPH0980193A REPROCESSING METHOD FOR SPENT FUEL 失效
公开(公告)号：JPH0980193A
公开(公告)日：1997-03-28
申请号：JP23526595
申请日：1995-09-13
申请人： HITACHI LTD
发明人： HOSHIKAWA TADAHIRO , SASAHIRA AKIRA , BABA TSUTOMU , FUKAZAWA TETSUO , KAMOSHITA MAMORU , KAWAMURA FUMIO
IPC分类号： G21C19/44 , G21F9/06
摘要： PROBLEM TO BE SOLVED: To provide a reprocessing method for spent fuel capable of easily changing the mixing ratio by recovering uranium and plutonium as uranium/ plutonium mixture. SOLUTION: After dissolving spent fuel into molten chloride 22 in a reaction tank 1, oxygen is supplied from an oxygen supply device 5 into the molten chloride 22 and Pu , Am , Np , UO2 are converted in their order is to PuO2 , Am2 O3 , NpO2 , U3 O8 and precipitated so that they are separated from the molten chloride 22 to recover.

36. 发明专利

JPH0933687A REPROCESSING METHOD FOR SPENT NUCLEAR FUEL 失效
公开(公告)号：JPH0933687A
公开(公告)日：1997-02-07
申请号：JP18880995
申请日：1995-07-25
申请人： HITACHI LTD
发明人： SASAHIRA AKIRA , HOSHIKAWA TADAHIRO , BABA TSUTOMU , FUKAZAWA TETSUO , KAMOSHITA MAMORU , KAWAMURA FUMIO
IPC分类号： G21C19/44 , C01G43/00 , C01G56/00
摘要： PROBLEM TO BE SOLVED: To separate and recover plutonium, americium, neptunium and uranium with the same equipment by supplying molten chloride, dissolved spent nuclear fuel with oxygen and converting those elements into undissolvable oxides in order. SOLUTION: First in a reaction tank 1, oxygen gas is supplied to spent nuclear fuel 5 and lithium chloride and potassium chloride by opening a valve 18 and the tank temperature is raised to dissolve the chlorides and then the fuel 5 is dissolved in it. Then, a filter 3a is drawn up with a driving motor control dial 14 and undissolvable residue and the like are recovered. By opening a valve 19, oxygen is gradually supplied to the reaction tank 1. When oxygen ion concentration becomes such that plutonium converts to oxide, the concentration no more increases even with the increase of the integral amount of supplied oxygen. When plutonium is depleted, it again starts rising. Then, the supply of oxygen is stopped and a filter 3b is drawn up to recover plutonoim deposit. In the same manner, ion concentrations are raised and oxide deposits of americium, neptunium and uranium are separated and recovered in turn.

37. 发明专利

JPH07159589A SEPARATING METHOD FOR TRANSPLUTONIUM ELEMENTS 失效
公开(公告)号：JPH07159589A
公开(公告)日：1995-06-23
申请号：JP30497593
申请日：1993-12-06
申请人： HITACHI LTD
发明人： KAMOSHITA MAMORU , FUKAZAWA TETSUO , KAWAMURA FUMIO
IPC分类号： G21C19/46
摘要： PURPOSE:To efficiently separate trans-Pu elements by adjusting the trans-Pu elements having the trivalence in an aqueous solution to the extractive valence, and keeping fission product nuclear species at the unextracted state. CONSTITUTION:O3 is fed into a nitric acid radioactive waste liquid generated by the reprocessing of the spent fuel, and the fission product nuclear species are oxidized to the high-valence state. Ammonium peroxodisulfate is added to oxidize Am to the tetravalance. U and Pu not recovered by reprocessing and Np are made the tetravalance. Tributyl phosphoric acid is used as the extracting agent for solvent extraction. Am and tetravalent actinoids are extracted and separated from the waste liquid. The organic phase after the solvent extraction is scrubbed with a nitric acid aqueous solution, and the fission product nuclear species are decontaminated. A stripping liquid containing a reducing agent such as nitrous acid is used for stripping while Am is reduced to the pentavalence or trivalence and Np is reduced to the pentavalence, Finally Am is made trivalence, Np is made pentavalence, and U and Pu are removed by bringing into contact with tributyl phosphoric acid for purification.

38. 发明专利

JPH06265695A METHOD FOR TREATING RADIOACTIVE WASTE LIQUID 失效
公开(公告)号：JPH06265695A
公开(公告)日：1994-09-22
申请号：JP4978893
申请日：1993-03-11
申请人： HITACHI LTD
发明人： SASAHIRA AKIRA , HOSHIKAWA TADAHIRO , FUKAZAWA TETSUO , NAKAMURA TOMOTAKA
IPC分类号： G21F9/06 , C02F1/70 , C02F1/72
摘要： PURPOSE:To control the shift of a high level waste liquid concentration process of radioactive ruthenium to a low level waste liquid evaporation process by expelling nitrous acid in a case where nitric acid concentration in a nitric acid solution is at a specific value or more. CONSTITUTION:A storage tank 1 of radioactive waste liquid stores the radioactive waste liquid containing ruthenium. In another storage tank 2 of a nitrous acid expelling agent, the expelling agent reacts with nitrous acid of one or more out of urea, hydroxylamine and the like and substance for analyzing nitrous acid or a solution of its substance is stored. The radioactive liquid is transmitted to an electrolytic cell 3, ruthenium is oxidized with submerged electrodes and reduced. A pH meter 4 measures pH of the radioactive waste liquid in the electrolytic cell 3 and the nitrous acid expelling agent is supplied to the electrolytic cell 3 because nitric acid is at normal of 0.001 in a case where pH is 3 or less. Ruthenium of the electrolytic cell 3 is oxidized and next insoluble ruthenium is produced by reducing to ruthenium. And the radioactive waste in the electrolytic cell 3 is transmitted to a filter 5 and separated into filtrate 6 and the insoluble ruthenium 7.

39. 发明专利

JPH06180386A MANAGING METHOD FOR REPROCESSING PROCESS 失效
公开(公告)号：JPH06180386A
公开(公告)日：1994-06-28
申请号：JP33409592
申请日：1992-12-15
申请人： HITACHI LTD
发明人： FUKAZAWA TETSUO , NAKAMURA TOMOTAKA
IPC分类号： G21C19/42
摘要： PURPOSE:To transfer a product or impurities under optimal state between processes or machines by analyzing the composition of solution discharged from a process and then determining destination of the solution based on the results of analysis. CONSTITUTION:Product solution 1 containing impurities is introduced to a process 2 for removing impurities from the product and discharged from the process 2 after the impurities are removed. In this regard, a part of the product solution 1 discharged to an analyzer 5 is sampled and the impurity concentration of sampled solution 6 is measured. Magnitude of measurement is then decided and a control signal 7 is delivered to a three-way valve 8. Consequently, the product solution 1 is transferred to process 3 or 4 depending on the impurity concentration of solution processed through the process 2. This method allows normal management of process (under optimal state) while transferring the solution to a process optimal for the composition thereof.

40. 发明专利

JPH0666989A EFFECTIVE NOX UTILIZATION TYPE REPROCESSING 失效
公开(公告)号：JPH0666989A
公开(公告)日：1994-03-11
申请号：JP22169992
申请日：1992-08-20
申请人： HITACHI LTD
发明人： FUKAZAWA TETSUO , KAWAMURA FUMIO
IPC分类号： G21C19/46
摘要： PURPOSE:To effectively utilize NOX in a reprocessing by using NOX on nitrous acid generated in the dissolution reaction for spent fuel or radiolysis reaction of nitric acid for controlling the valence of the dissolved material in nitric acid solution in the reprocessing. CONSTITUTION:In the NOX generation process 1 in a reprocessing nitrous acid is produced due to the dissolution reaction of nitric acid 2. It eventually becomes to NOX and moves to gas phase gas 6. It is transported as it is or after being purified by eliminating the co-existing matter included in it with a co-existing matter eliminating device 5 or being purified to some extent, to a valence control process 3 in the reprocessing process as NOX gas 7. In the process 3, by bowing in NOX, the valence state of solved material in the nitric acid 4 is converted into the state proportional to the electric potential of NOX. Thus, by transporting the NOX generated in the process 1 to process 3, the dissolved material in the process 3 is oxidized or reduced.

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