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1. 发明专利

JP2006206334A Hydrogen producing apparatus and hydrogen producing method 审中-公开
标题翻译：氢生产装置和氢生产方法
公开(公告)号：JP2006206334A
公开(公告)日：2006-08-10
申请号：JP2005016206
申请日：2005-01-25
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： SASAHIRA AKIRA , KARASAWA HIDETOSHI , HOSHINO KUNIYOSHI
IPC分类号： C01B3/06 , C01B3/02
CPC分类号： Y02E60/36
摘要： PROBLEM TO BE SOLVED: To provide a hydrogen producing apparatus and a hydrogen producing method by which hydrogen can be efficiently produced regardless of the temperature of a heat source used in production of hydrogen. SOLUTION: The hydrogen producing apparatus 1a comprises: a high temperature gas furnace 2 (first heat source); a hydrogen production section where hydrogen is produced by accelerating the reduction reaction of water with sulfur dioxide by heat supplied from the high temperature gas furnace 2; and a sulfur trioxide decomposer 17 which reproduces sulfur dioxide by decomposing sulfur trioxide produced as a by-product by the reduction reaction in the hydrogen production section and which supplies the reproduced sulfur dioxide to the hydrogen production section, and further comprises an electric heater 17a which is a second heat source different from the high temperature gas furnace 2, wherein the sulfur trioxide decomposer 17 decomposes sulfur trioxide by heat supplied from the electric heater 17a. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供氢制造装置和氢制造方法，通过该方法可以有效地制造氢，而与用于制造氢的热源的温度无关。解决方案：制氢装置1a包括：高温气体炉2（第一热源）; 通过从高温气体炉2供给的热量加速二氧化硫的还原反应而产生氢的氢气生成部; 和三氧化硫分解器17，其通过在氢气产生部分中通过还原反应分解作为副产物产生的三氧化硫并且将再生的二氧化硫供应到氢气产生部分来再生二氧化硫，并且还包括电加热器17a，其中是与高温气体炉2不同的第二热源，其中三氧化硫分解器17通过从电加热器17a供给的热分解三氧化硫。版权所有（C）2006，JPO＆NCIPI

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

JP2002071865A MANUFACTURING METHOD FOR MIXED OXIDE FUEL FOR NUCLEAR REACTOR 失效
公开(公告)号：JP2002071865A
公开(公告)日：2002-03-12
申请号：JP2000267454
申请日：2000-09-04
申请人： HITACHI LTD
发明人： KAMOSHITA MAMORU , SASAHIRA AKIRA , KANI YUKO
IPC分类号： G21C3/62 , G21C19/44 , G21F9/02
摘要： PROBLEM TO BE SOLVED: To provide a manufacturing method for mixed oxide fuel for a nuclear reactor capable of quickly and easily securing a uniform mixing property of uranium and plutonium. SOLUTION: Mixed gas of plutonium hexafluoride and uranium hexafluoride is generated (process 7), the mixed gas is reacted with water vapor to generate a mixture granule of uranium oxide and plutonium oxide (process 8) and fuel for the reactor is manufactured by using the granule (process 9).

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

JPH06293982A BOILING WATER TYPE NUCLEAR REACTOR AND METHOD FOR PREVENTING CORROSION OF ITS STRUCTURAL MATERIAL 失效
公开(公告)号：JPH06293982A
公开(公告)日：1994-10-21
申请号：JP7978193
申请日：1993-04-06
申请人： HITACHI LTD
发明人： TAKAHASHI MASANORI , IBE HIDEFUMI , SASAHIRA AKIRA , WATANABE ATSUSHI
IPC分类号： C23F13/00 , C23F13/12 , C23F13/20 , G21D1/00
摘要： PURPOSE:To prevent the corrosion of the core structural materials of a boiling water reactor with which the relaxation of corrosive environment is difficult while suppressing the migration of N which is radioactive nitrogen to a turbine system. CONSTITUTION:The core section 1 of the boiling water reactor is provided with electrodes 10 in the reactor water and the potential of the core structural materials is decreased to N into the turbine system is suppressed. As a result, the corrosion of the core structural materials is lessened while the radiation dose of main steam system pipings and the turbine system and eventually the dose rate of site boundaries are suppressed.

6. 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.

7. 发明专利

JPS63307103A METHOD FOR REMOVING RUTHENIUM IN NITRIC ACID SOLUTION 失效
公开(公告)号：JPS63307103A
公开(公告)日：1988-12-14
申请号：JP14314487
申请日：1987-06-10
申请人： HITACHI LTD
发明人： KAWAMURA FUMIO , SASAHIRA AKIRA
IPC分类号： C01B21/46 , C01B21/26 , C01G55/00
摘要： PURPOSE:To enable effective removal of corrosion accelerating Ru ions, by adding an oxidizing agent into a nitric acid solution containing the Ru. CONSTITUTION:Although Ru ions contained in a nitric acid solution are mostly present as a nitrosyl ions assuming the form of RuNO , the ions are partially oxidized into RuO4 by oxidizing power of nitric acid to accelerate corrosion of equipment structural materials. As a result, an oxidizing agent, e.g. O3 or O2, is blown into the nitric acid solution to convert the RuO4 is extremely volatile, the formed RuO4 is rapidly volatilized to migrate from the nitric acid solution to the vapor phase and almost 100% of RuNO and RuO4 in the liquid phase is removed.

8. 发明专利

JPS6332398A STORAGE TANK FOR HIGH RADIOACTIVE SUBSTANCE 失效
公开(公告)号：JPS6332398A
公开(公告)日：1988-02-12
申请号：JP17563086
申请日：1986-07-28
申请人： HITACHI LTD
发明人： IZUMIDA TATSUO , SASAHIRA AKIRA , NISHI TAKASHI
IPC分类号： G21F9/22 , G21C19/46

9. 发明专利

JP2006282413A Hydrogen production system 审中-公开
标题翻译：氢生产系统
公开(公告)号：JP2006282413A
公开(公告)日：2006-10-19
申请号：JP2005100960
申请日：2005-03-31
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： SHIINA KOJI , KARASAWA HIDETOSHI , SASAHIRA AKIRA , HOSHINO KUNIYOSHI
IPC分类号： C01B3/38 , G21D9/00
CPC分类号： Y02P20/129
摘要： PROBLEM TO BE SOLVED: To provide a technology which is related to a hydrogen production system using waste heat from spent nuclear fuel in an atomic power station, which is particularly suitable for the effective utilization of energy and where temperature fitting to reaction conditions in hydrogen production can be suitably controlled. SOLUTION: The hydrogen production system (50) is equipped with a heat generator (1) to seal a nuclear waste releasing waste heat and a hydrogen producer (18) to produce hydrogen (F) using the waste heat as reaction heat and has an intermediate heat exchanger (10) where the waste heat is transferred for heating, a primary fluid (A) to transfer the waste heat by recycling it between the heat generator (1) and the intermediate heat exchanger (10) and a secondary fluid (B) to transfer the reaction heat by recycling it between the hydrogen producer (18) and the intermediate heat exchanger (10). COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种与在原子能发电站中使用来自乏核燃料的废热的氢气生产系统有关的技术，其特别适用于有效利用能量以及适合于反应条件的温度在氢气生产中可以适当控制。解决方案：氢气生产系统（50）装备有用于将废热排放废热和氢气生产器（18）的热发生器（1）用废热作为反应热产生氢气（F），具有中间热交换器（10），其中废热被传送用于加热，主流体（A）通过在发热器（1）和中间热交换器（10）之间再循环来传递废热，并且辅助流体（B）通过在氢气生产器（18）和中间热交换器（10）之间循环来传递反应热。版权所有（C）2007，JPO＆INPIT

10. 发明专利

JP2005195498A Method and device for reprocessing spent nuclear fuel 有权
标题翻译：代替核燃料燃料的方法和装置
公开(公告)号：JP2005195498A
公开(公告)日：2005-07-21
申请号：JP2004003146
申请日：2004-01-08
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： HOSHINO KUNIYOSHI , SASAHIRA AKIRA , KAWAMURA FUMIO
IPC分类号： G21C19/44
CPC分类号： Y02W30/882
摘要： PROBLEM TO BE SOLVED: To continuously perform a process for separating U and Pu from spent nuclear fuel. SOLUTION: Spent nuclear fuel and a fluorinating agent are continuously supplied to a flame-type reactor 2 so that the nuclear fuel is on the center side while the fluorinating agent is around the spent fuel. The amount of fluorinating agent supplied is controlled so as to be 1.3 to 1.5 times of an amount necessary for fluorination reaction of supplied spent nuclear fuel based on the amount of supplied spent nuclear fuel. The temperature of spent nuclear fuel may once be kept at 200 to 400°C (473 to 673°K), the nuclear fuel including uranium and plutonium after the fluorination reaction. COPYRIGHT: (C)2005,JPO&NCIPI

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