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1. 发明专利

JP2003202394A OPTICAL HYBRID POWER GENERATION 审中-公开
公开(公告)号：JP2003202394A
公开(公告)日：2003-07-18
申请号：JP2001401854
申请日：2001-12-28
申请人： TOKYO ELECTRIC POWER CO , TOSHIBA CORP
发明人： TAKIZAWA YASUSHI , AMANO OSAMU , FUKUSHIMA KIMICHIKA , YOKOYAMA TSUGIO , IIDA NORIHIKO , NODA ETSUO
IPC分类号： G21D7/00 , G21H3/00
摘要： PROBLEM TO BE SOLVED: To drastically improve energy utilization efficiency by converting in large scale from fission energy to light. SOLUTION: The fission energy discharged from nuclear fuel is converted to energy of electrons existing in luminous body and the energy of electrons is converted to light in luminous system 4. A optical power generation system 2 is constituted of the luminous system 4 and a power generation system 6 for converting the light to electricity. A heat power generation system 3 for generating power by utilizing the heat energy not converted from the electron energy to light is also provided. COPYRIGHT: (C)2003,JPO

2. 发明专利

JP2004233066A Reprocessing method for spent nuclear fuel 有权
公开(公告)号：JP2004233066A
公开(公告)日：2004-08-19
申请号：JP2003018522
申请日：2003-01-28
申请人： Hitachi Ltd , Tokyo Electric Power Co Inc:The , 東京電力株式会社 , 株式会社日立製作所
发明人： KAWAMURA FUMIO , HOSHINO KUNIYOSHI , AOI MASAKATSU , SASAHIRA AKIRA , AMANO OSAMU , KOBAYASHI HIROAKI
IPC分类号： G21C19/44 , C01G56/00
CPC分类号： C01G56/006 , C01G56/005
摘要： PROBLEM TO BE SOLVED: To improve a reprocessing speed of spent nuclear fuel and obtain a mixture of high-purity uranium and reusable plutonium in a simple process at low cost.
SOLUTION: Spent nuclear fuel 1 is fluorinated with fluorine 2 in a fluorination process 3 and the mixture of uranium and plutonium and fission products are separately recovered. The plutonium fluoride volatilizing in fluorination process is recovered together with a stabilization agent, and after passing an oxidation conversion process 8, recovered as a mixed oxide of uranium and plutonium. Since uranium is recovered at a high purity, control in reuse, storage and the like is very easy. As they are recovered as the mixture of uranium and plutonium, fuel refabrication cost can be lowered and non-proliferation characteristic can be increased. Due to dry type, device and processing facility can be made simple and so economy is improved and fuel refabrication cost can be lowered.
COPYRIGHT: (C)2004,JPO&NCIPI

3. 发明专利

JP2003054902A Photocatalyst use type hydrogen/oxygen manufacturing method using radiation and apparatus therefor 审中-公开
标题翻译：光催化剂使用类型氢/氧气制造方法使用其辐射和装置
公开(公告)号：JP2003054902A
公开(公告)日：2003-02-26
申请号：JP2001241794
申请日：2001-08-09
申请人： Japan Atom Energy Res Inst , Tokyo Electric Power Co Inc:The , 日本原子力研究所 , 東京電力株式会社
发明人： KAWAMURA HIROSHI , UCHIDA MUNENORI , YAMADA KOICHI , AMANO OSAMU
IPC分类号： G21H3/00 , B01J23/648 , B01J35/02 , C01B3/04 , C01B13/02 , G21H5/00
CPC分类号： Y02E60/364
摘要： PROBLEM TO BE SOLVED: To provide a method and an apparatus for producing hydrogen/oxygen particularly using a radioactive substance produced from a nuclear reactor or the like in the treatment of high level radioactive waste produced from the nuclear reactor or the like. SOLUTION: The following technical contents are provided as the constituting requirements of this invention. A radioactive material produced in the nuclear reactor or the like attenuates its radioactivity with the emission of γ. X-ray. The γ. X-ray is transformed to visible ray or ultraviolet ray by a scintillator. Water is decomposed by irradiating a photocatalyst with the visible ray or the ultraviolet ray to produce hydrogen and oxygen. The waste is stored in a water tank until the radioactivity is sufficiently attenuated to produce hydrogen and oxygen and after that, the waste is sent to a normal treatment process such as reclamation. The manufacturing apparatus is provided with a vessel for mixing and preserving the scintillator and the waste in the water tank and an apparatus for recovering the produced hydrogen and oxygen and can be constructed within the extent to which a conventional preserving apparatus is extended.
摘要翻译：要解决的问题：提供一种用于生产氢/氧的方法和装置，特别是使用由核反应堆等制造的放射性物质来处理从核反应堆等产生的高放射性废物。解决方案：提供以下技术内容作为本发明的构成要求。在核反应堆等中产生的放射性物质以γ的发射衰减其放射性。 X光片。 γ。 X射线被闪烁体转变成可见光或紫外线。通过用可见光或紫外线照射光催化剂来分解水分以产生氢和氧。将废物储存在水箱中，直到放射性充分减弱以产生氢气和氧气，然后将废物送至正常的处理过程如回收。制造装置设置有用于混合和保存水箱中的闪烁体和废物的容器，以及用于回收所产生的氢和氧的装置，并且可以在传统的保存装置延伸的程度内构造。

4. 发明专利

JP2003098291A METHOD FOR DRY REPROCESSING OF SPENT NUCLEAR FUEL 审中-公开
公开(公告)号：JP2003098291A
公开(公告)日：2003-04-03
申请号：JP2001294653
申请日：2001-09-26
申请人： MITSUBISHI HEAVY IND LTD , TOKYO ELECTRIC POWER CO , HOKKAIDO ELECTRIC POWER , TOHOKU ELECTRIC POWER CO , CHUBU ELECTRIC POWER , HOKURIKU ELECTRIC POWER , KANSAI ELECTRIC POWER CO , CHUGOKU ELECTRIC POWER , SHIKOKU ELEC POWER , KYUSHU ELECTRIC POWER , JAPAN ATOMIC POWER
发明人： HARA TERUO , OWAYA HIDENARI , AMANO OSAMU , SUDO KUNIHIKO , KOSAKA YUJI , SHIMADA TAKASHI
IPC分类号： G21C19/44 , G21C19/34 , G21C19/37
摘要： PROBLEM TO BE SOLVED: To quickly separate spent nuclear fuel from a clad tube. SOLUTION: The method comprises a step (S3) of forming an opening portion in the clad tube in which spent nuclear fuel is hermetically filled, and a step (S4) of heat-treating the spent nuclear fuel together with the clad tube under a gas atmosphere containing oxygen (O2 ) at 450 to 800 deg.C. The method is used when separating spent nuclear fuel generated by a fusion layer adhering to the clad tube from the clad tube. This method can quickly oxidize and powder the spent nuclear fuel.

5. 发明专利

JP2003098290A DRY METHOD OF REPROCESSING SPENT NUCLEAR FUEL 审中-公开
公开(公告)号：JP2003098290A
公开(公告)日：2003-04-03
申请号：JP2001294652
申请日：2001-09-26
申请人： MITSUBISHI HEAVY IND LTD , TOKYO ELECTRIC POWER CO , HOKKAIDO ELECTRIC POWER , TOHOKU ELECTRIC POWER CO , CHUBU ELECTRIC POWER , HOKURIKU ELECTRIC POWER , KANSAI ELECTRIC POWER CO , CHUGOKU ELECTRIC POWER , SHIKOKU ELEC POWER , KYUSHU ELECTRIC POWER , JAPAN ATOMIC POWER
发明人： HARA TERUO , OWAYA HIDENARI , AMANO OSAMU , SUDO KUNIHIKO , KOSAKA YUJI , SHIMADA TAKASHI
IPC分类号： G21C19/44
摘要： PROBLEM TO BE SOLVED: To reduce an amount of a glass solidified body for solidifying a radio- active waste generated in a spent nuclear fuel. SOLUTION: This method is provided with a step (S4) for oxidation-heating the spent nuclear fuel at 450-800 deg.C to generate fuel powder, and a step (S6) for heat-treating the fuel powder at 1000 deg.C or more under a reduced pressure atmosphere to separate a volatile substance volatilized and a non-volatile substance not volatilized. Cesium 137 of a radio-active nuclear species generated by combustion of the nuclear fuel is contained in the volatile substance. Radio- activity is reduced and a heating value is reduced in the radio-active waste generated by reprocessing, by conducting the separation into the volatile substance and the non-volatile substance (S4) to reprocess the non-volatile substance (S7).

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