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1. 发明专利

JPH10111390A DISSOLVER 失效
公开(公告)号：JPH10111390A
公开(公告)日：1998-04-28
申请号：JP26308396
申请日：1996-10-03
申请人： MITSUBISHI HEAVY IND LTD
发明人： KAWAMURA WATARU , MIYAKE TAKASHI , MURASAWA KENJI , FUJIOKA TSUNAAKI , KANEDA MASAKAZU , OKAZAKI KIKUO
IPC分类号： G21C19/46
摘要： PROBLEM TO BE SOLVED: To keep sludge unapt to adher or deposit in a reprocessing process of a nuclear fuel and enable the promotion of solution reaction by forming an inner face of a bottom part of a dissolver main body on a curved face and sending fluid from a fluid introducing tube toward a curved face of the bottom part. SOLUTION: An inner face of a bottom part of a dissolver main body 1 is formed on a curved face. Nitride solution is filled in the dissolver main body 1, irradiated fuel is changed, and the whole dissolver main body 1 is heated. With heating, a gas supply unit 4 is operated, and gas is sent toward a curved face of the bottom part 2 by a gas introducing tube 3. The sent gas flows along a curved face of the bottom part 2, and the solution near the bottom part 2 is flowed upwardly. At this time, a sludge floating in the solution or a sludge to be laminated on the bottom part 2 flows upwardly with gas and solution, and the sludge is hardly laminated on the bottom part 2. The solution is stirred by flowing of the solution generated when the fluid is sent, the opportunity of contact with fuel and nitride is enhanced, and dissolution reaction is promoted.

2. 发明专利

JP2002022883A DISSOLVING METHOD FOR POORLY SOLUBLE NUCLEAR FUEL 失效
公开(公告)号：JP2002022883A
公开(公告)日：2002-01-23
申请号：JP2000208597
申请日：2000-07-10
申请人： MITSUBISHI HEAVY IND LTD , NUCLEAR DEV CORP
发明人： MIYAKE TAKASHI , KAWAMURA WATARU , MURASAWA KENJI , FUJIOKA TSUNAAKI , MIYATA MASAHARU
IPC分类号： G21C19/46
摘要： PROBLEM TO BE SOLVED: To efficiently dissolve-poorly soluble nuclear fuel including plutonium in a short time. SOLUTION: To poorly soluble nuclear fuel including plutonium oxide, dissolving 3 in high temperature nitric acid in diluted nitric acid near the boiling temperature is applied. The solution is separated into filtrate A7 and insoluble residue A9 by solidliquid separation 5, electrodissolution 11 is applied to the insoluble residue A9 and it is separated into filtrate B15 and insoluble residue B.

3. 发明专利

JPH11248880A METHOD FOR TREATING SPENT FUEL 失效
公开(公告)号：JPH11248880A
公开(公告)日：1999-09-17
申请号：JP5550798
申请日：1998-03-06
申请人： MITSUBISHI HEAVY IND LTD , NEW CLEAR DEV KK
发明人： FUJIOKA TSUNAAKI , IIZUKA TATSUYA , KOSAKA YUJI
IPC分类号： G21C3/62 , G21C19/44
摘要： PROBLEM TO BE SOLVED: To collect uranium in the form of nitride by heating a spent fuel with uranium nitride as a main constituent in a nitrogen atmosphere containing N that is at least a specific nitrogen partial pressure at a specific temperature of a specific amount of time and removing the covering of uranium nitride and pulverizing it and at the same time separating and eliminating a volatile unclear reaction product. SOLUTION: A reaction container 2 is provided with a nitrogen gas supply line 4 for supplying a nitrogen gas containing N to a reaction container 2, an inert gas supply line 5 for supplying an inert gas to the reaction container 2, a gas exhaust line 6, and a heating heater 3, and heats a spent fuel 1 in a nitrogen gas atmosphere. In this configuration, the spent fuel that mainly consists of uranium nitride is heated for approximately 10-30 minutes within the range of 600 deg.C-800 deg.C in a nitrogen gas atmosphere containing N where a nitrogen partial pressure is at least 0.01 atmospheric pressure, and then the spent fuel is heated at least for 30 minutes within the range of 800 deg.C-1,450 deg.C in an atmosphere where nitrogen is set to a partial pressure of 1 atmospheric pressure or less, vacuum, or inert gas atmosphere.

4. 发明专利

JPH0943390A PROCESSING METHOD FOR SPENT NUCLEAR FUEL 失效
公开(公告)号：JPH0943390A
公开(公告)日：1997-02-14
申请号：JP19953195
申请日：1995-08-04
申请人： MITSUBISHI HEAVY IND LTD
发明人： ENOKIDA YOICHI , FUJIOKA TSUNAAKI , AOKI KAZUO , HATANO MAMORU
IPC分类号： G21C19/44 , G21F9/02
摘要： PROBLEM TO BE SOLVED: To remove hydrogen, helium, krypton, xenon, etc., in nuclear fuel by reacting spent nuclear fuel with gas containing hydrogen, after reacting the pellet type spent nuclear fuel, whose major component is uranium nitrite, under such a state as heated with mixed gas of water vapor and oxygen. SOLUTION: Spent nuclear fuel 2 is heated in a reaction container 3 so as to react to reaction gas 4 containing water vapor and oxygen. Secondarily, nuclear fuel is heated in the same reaction container 3 or another reaction container 5 so that hydrogen, helium, krypton, xenon, iodine, and nitrogen are migrated into offgas 7 and recovered as the offgas 7 from the reaction containers 3, 5. Cubical expansion of the nuclear fuel 2 can physically spall a covered tube of the nuclear fuel 2 and allows to recover nitrogen from mixed gas of hydrogen, helium, etc., contained in the offgas 7 by a physical or chemical partition method 8.

5. 发明专利

JP2001194486A REPROCESSING METHOD FOR SPENT NUCLEAR FUEL 失效
公开(公告)号：JP2001194486A
公开(公告)日：2001-07-19
申请号：JP2000002510
申请日：2000-01-11
申请人： MITSUBISHI HEAVY IND LTD
发明人： MIYAKE TAKASHI , ISHIHARA NOBUO , OTA HIDEYUKI , FUJIOKA TSUNAAKI
IPC分类号： C01G43/01 , G21C19/44 , G21C19/46
摘要： PROBLEM TO BE SOLVED: To simplify a whole apparatus in reprocessing spent nuclear fuel by suppressing the generation radioactive wastes. SOLUTION: Spent fuel 31 of a light water reactor is made powder fuel 35 in an oxidation/powdering process. By using tributylphosphate-nitric acid complex 39, uranium-plutonium is selectively solved from the powder fuel 35 to gain uranium-plutonium solution liquid 41, which makes contact with nitric acid solution 51 to extract uranium-plutonium in reverse manner. The nitric acid solution 57 containing uranium-plutonium is purified and denitrated to be conversed into an oxide fuel 29.

6. 发明专利

JPH11231091A REPROCESSING METHOD FOR SPENT NUCLEAR FUEL 失效
公开(公告)号：JPH11231091A
公开(公告)日：1999-08-27
申请号：JP3505098
申请日：1998-02-17
申请人： MITSUBISHI HEAVY IND LTD , NEW CLEAR DEV KK
发明人： FUJIOKA TSUNAAKI , MIZUNO MINEO , IIZUKA TATSUYA
IPC分类号： G21C19/34 , G21C19/38
摘要： PROBLEM TO BE SOLVED: To efficiently disassemble a fuel rod when fuel for a light water nuclear reactor is reprocessed. SOLUTION: A fuel assembly 1 having a fuel rod in which fuel pellets are stored in a zirconium based alloy cladded pipe is sheared by a shearing machine 3 to form short fuel rod sheared pieces 5 to which hydrogen reducing heat treatment is applied in a rotary kiln 7 and then oxidizing heat treatment is applied in a rotary kiln 9. Additionally, a pelletized powder/cleadded pipe separator 11 separates pelletized powder 13 from cladded pipe pieces 15.

7. 发明专利

JPH11174194A METHOD FOR REPROCESSING NUCLEAR FUEL 失效
公开(公告)号：JPH11174194A
公开(公告)日：1999-07-02
申请号：JP34307997
申请日：1997-12-12
申请人： MITSUBISHI HEAVY IND LTD
发明人： FUJIOKA TSUNAAKI , OTA HIDEYUKI , MIYAKE TAKASHI
IPC分类号： G21C19/46
摘要： PROBLEM TO BE SOLVED: To simplify reaction processes and further reduce the volume of generated wastes in the reprocess of fuels. SOLUTION: Carbon dioxide is supplied from a carbon dioxide supplying line 5 to a dissolvent separation container 1, and the inside thereof is kept a carbon dioxide atmosphere in the temperature range between 35 deg.C and 100 deg.C and the pressure range from 75 to 300 atmospheric pressure. A fuel from a fuel supplying line 3, tri-n-butylphosphoric acid(TBP) from a supplying line 7 and nitric acid are reacted together. A TBP complex of uranium(U) and plutonium(Pu) is dissolved in the carbon dioxide in a super critical fluid to recover the from an exit line 11. fission product that does not form TBP complex and insoluble residue are separated by exhausting them from an exhaust line 13.

8. 发明专利

JPH10132989A SOLUTION TANK 失效
公开(公告)号：JPH10132989A
公开(公告)日：1998-05-22
申请号：JP29029396
申请日：1996-10-31
申请人： MITSUBISHI HEAVY IND LTD
发明人： NATSUME TOSHIHIRO , FUJIOKA TSUNAAKI
IPC分类号： G21C19/40 , G21C19/46
摘要： PROBLEM TO BE SOLVED: To reduce the quantity of radioactive waste so that the non-critical property of a solution tank can be kept even when a basket is enlarged by constituting the basket to be housed within a solution tank body by use of a fixed neutron absorbing material, and partitioning the inner part of the basket by a partitioning member of fixed neutron absorbing material into sections having a specified dimension. SOLUTION: A basket 2 to be housed within a solution tank body 1 for dissolving the fuel sheared pieces of a spent fuel assembly with a dissolving solution such as nitric acid is formed of a fixed neutron absorbing material. A partitioning member 3 formed of a fixed neutron absorbing material is set within the basket 2. The partitioning member 3 is formed into grid, cross or cylindrical form. The inner dimension of each section formed by the partitioning member 3 is set to 10-20cm. As the fixed neutron absorbing material, boron stainless, hafnium or the like is used. Thus, it is not required to acid a soluble neutron absorbing material such as gadolinium nitrate to a dissolving solution such as nitric acid, and the quantity of radioactive waste can be reduced.

9. 发明专利

JPH0568974A TREATMENT OF BORIC ACID-CONTAINING SOLUTION 失效
公开(公告)号：JPH0568974A
公开(公告)日：1993-03-23
申请号：JP23308591
申请日：1991-09-12
申请人： MITSUBISHI ATOMIC POWER IND , MITSUBISHI HEAVY IND LTD
发明人： FUJIOKA TSUNAAKI , NAKAHARA TAKASHI , MATSUMOTO HIROYO , MURAKAMI OSAMU
IPC分类号： B01D61/58 , C01B35/10 , C02F1/44 , G21F9/06
摘要： PURPOSE:To reduce the volume of waste by providing three stages of reverse osmosis membrane module and reducing the content of impurity in the liquid waste and boric acid-containing solution such as used fuel pit water in an atomic power plant to the reference value of water reutilization of a nuclear reactor. CONSTITUTION:A reverse osmosis membrane (R/O membrane) circulating solution tank 1 storing a boric acid-containing solution is provided and the first - third stage R/O membrane module 4-6 having different separation factors to components in the boric acid-containing solution, for example, boric acid, silica and chlorine are provided and all of them are connected in a cascade state. The boric acid-containing solution is applied by a high pressure supply pump 2 and, after the solid in the treated solution is removed in an ultrafiltration filter module 3, the treated solution is sent to the first stage module 4 and the transmitted recovered solution taken out on the secondary side thereof is supplied to the respective module 5, 6. The transmitted solutions of the module 5, 6 are returned to the tank 1 as untreated boric acid-containing solutions and the solution remaining on the primary side of the module 6 is recovered as a conc. waste solution.

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