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1. 发明专利

JP2003344578A Recycle system for zirconium waste 有权
标题翻译： ZIRCONIUM WASTE循环系统
公开(公告)号：JP2003344578A
公开(公告)日：2003-12-03
申请号：JP2002152371
申请日：2002-05-27
申请人： Toshiba Corp , 株式会社東芝
发明人： FUJITA REIKO , NAKAMURA HITOSHI , MIZUGUCHI KOJI , HIROSE EMIKO , SHIBANO TAKAYUKI , NATSUI KAZUJI , MATSUMOTO KOICHI , HAYASHIDA YOSHIHISA
IPC分类号： G21C19/44 , C22B34/14 , C25C3/26 , C25C3/34
CPC分类号： Y02P10/212 , Y02W30/882
摘要： PROBLEM TO BE SOLVED: To recover uranium and transuranium elements from a cladding tube and a channel box contaminated with uranium and transuranium elements and recover zirconium at a high purity. SOLUTION: The cladding tube and cladding hulls 25 of the channel box contaminated with uranium (U) and transuranium elements (TRU) are contained in an anode basket 20 and dipped in a molten salt. KCl-LiCl-ZrCl 2 having a low UO 2 solubility is used as the molten salt. Fused-salt electrolysis is executed in an electrolytic cell 18 by using iron or molybdenum as a cathode 19. Nb, Mo and Co which are contamination nuclides are recovered at the first cathode. When Zr starts depositing, the first cathode is replaced with the second cathode to deposit and recover metallic Zr at the second cathode. In the case of metallic uranium and transuranium elements adhering, they remain in the molten salt, and oxide settles as precipitate 28 on a bottom plate of the electrolytic cell 18 and is recovered. COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：从铀和铀元素污染的包层管和通道箱中回收铀和铀元素，并以高纯度回收锆。解决方案：被铀（U）和铀元素（TRU）污染的通道箱的包层管和包壳25被包含在阳极筐20中并浸入熔融盐中。使用具有低UO 2 溶解度的KCl-LiCl-ZrCl 2 作为熔融盐。通过使用铁或钼作为阴极19在电解槽18中进行熔盐电解。在第一阴极回收作为污染核素的Nb，Mo和Co。当Zr开始沉积时，第一阴极被第二阴极替代，以在第二阴极沉积和回收金属Zr。在金属铀和超铀元素附着的情况下，它们保留在熔融盐中，并且氧化物作为沉淀物28沉降在电解槽18的底板上并被回收。版权所有（C）2004，JPO

2. 发明专利

JP2005321252A Method for measuring distribution of void rate in boiling water reactor 有权
标题翻译：用于测量锅炉水反应器中无效率分布的方法
公开(公告)号：JP2005321252A
公开(公告)日：2005-11-17
申请号：JP2004138236
申请日：2004-05-07
申请人： Toshiba Corp , 株式会社東芝
发明人： KIKUCHI TSUKASA , UEDA KIYOSHI , MIHASHI TAKESHI , HAYASHIDA YOSHIHISA , KUROSAWA MASAHIKO
IPC分类号： G21C17/02 , G21C17/038
摘要： PROBLEM TO BE SOLVED: To obtain a method for measuring void rates which makes it possible to easily measure a void rate inside a core and an effective void rate on the outer periphery in a boiling water reactor with an existing actual device without installing any new jigs for measurement, producing distortions of neutron flux or output or causing the loss of the reactivity in the core. SOLUTION: Given a threshold energy causing an activation reaction by fast neutrons whose energy is a certain value or higher, the reactivity ratio[(F)/(S)] of the fast neuron activation reactivity (F) of fast neutron threshold reaction nuclides to the slow neutron activation reactivity (S) in the activation of slow neutrons consisting of thermal and epithermal neutrons through the absorption of them is measured to a void rate measurement position (x) and a position (0) of a known void rate. Then, the reactivity ratio R=[(Fx)/(Sx)]/[(Fo/So)] of the reactivity ratio (Fx)/(Sx) of the void rate measurement position (x) to the reactivity ratio (Fo/So) of the position (0) of the known void rate is determined and is used together with a calibration curve found otherwise to determine the axial distribution of void rates of the reactor. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为了获得一种用于测量空隙率的方法，其使得可以容易地测量具有现有实际装置的沸水反应堆中的芯内的空隙率和外周上的有效空隙率，而无需安装任何新的测量夹具，产生中子通量或输出失真或引起芯体反应性的损失。解决方案：考虑到能量为一定值或更高的快中子引起活化反应的阈值能量，快中子阈值的快速神经元激活反应性（F）的反应性比[（F）/（S）] 将通过其吸收由热和超热中子组成的缓慢中子活化的缓慢中子活化反应性（S）的反应核素测量为空隙率测量位置（x）和已知孔隙率的位置（0）。然后，空隙率测定位置（x）与反应性比例（Fo）的反应性比（Fx）/（Sx））的反应性比R = [（Fx）/（Sx）] / [（Fo / 确定了已知空隙率的位置（0）），并且与校准曲线一起使用，否则确定反应器的空隙率的轴向分布。版权所有（C）2006，JPO＆NCIPI

3. 发明专利

JP2003344586A Disposal container and disposal method for radioactive waste 审中-公开
标题翻译：放射性废物处理容器和废弃处理方法
公开(公告)号：JP2003344586A
公开(公告)日：2003-12-03
申请号：JP2002150871
申请日：2002-05-24
申请人： Toshiba Corp , 株式会社東芝
发明人： HIROSE EMIKO , NATSUI KAZUJI , SHIBANO TAKAYUKI , MATSUMOTO KOICHI , FUJITA REIKO , HAYASHIDA YOSHIHISA
IPC分类号： G21F9/36 , B09B1/00 , G21F9/34
摘要： PROBLEM TO BE SOLVED: To obtain a radioactive waste disposal container hardly corroded compared with conventional steel vessel and capable of retaining nuclides for a long time and obtain a disposal method for preventing contamination from the outer surface of the disposal container during a series of works for disposal.
SOLUTION: The radioactive waste disposal container for the burial disposal of radioactive waste in the underground is constituted of Zircaloy.
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：为了获得与常规钢容器相比几乎不腐蚀并且能够长时间保留核素的放射性废物处理容器，并获得用于防止一系列处理容器的外表面污染的处置方法的作品处置。解决方案：埋地放射性废物处置放射性废物处理容器由Zircaloy组成。版权所有（C）2004，JPO

4. 发明专利

JP2002311147A NEUTRON SPECTRUM MEASURING DEVICE AND NEUTRON DETECTOR 失效
公开(公告)号：JP2002311147A
公开(公告)日：2002-10-23
申请号：JP2001119160
申请日：2001-04-18
申请人： TOSHIBA CORP
发明人： HAYASHIDA YOSHIHISA
IPC分类号： G01T3/00
摘要： PROBLEM TO BE SOLVED: To solve the problem that a proper neutron spectrum cannot be found because the measuring condition of each neutron detector is not identical when the size of the neutron detector having the different thickness of a moderator used to measure different neutron energies is different in such a way that the distribution of a neutron flux is not uniform. SOLUTION: The neutron detector 1b is constituted in such a way that a support member 5b is installed at the outside of a thermal neutron detector 2 and that a thermal neutron absorber 4 is installed additionally at the outside of the moderator 3b. The thickness of the support member 5b is adjusted so as to match the thickness of the moderator 3b, and the size of the neutron detector 1b is made identical to the size of other neutron detectors in the neutron spectrum measuring device. Thereby, irrespective of the thickness off the moderator, the size of the neutron detectors becomes identical, and the proper neutron spectrum can be found and measured.

5. 发明专利

JPH05209995A EVALUATION SUPPORT SYSTEM FOR REQUIRED APPROXIMATE DIMENSIONS OF SHIELD 失效
公开(公告)号：JPH05209995A
公开(公告)日：1993-08-20
申请号：JP1608892
申请日：1992-01-31
申请人： TOSHIBA CORP
发明人： HAYASHIDA YOSHIHISA
IPC分类号： G21F7/00
摘要： PURPOSE:To determine the approximate required dimensions of a shield automatically and in a short time by evaluating the approximate shielded wall thickness and ceiling thickness of a new facility on the basis of the design data of an existing facility, the design condition of the new facility, or the like. CONSTITUTION:An operating means 4 generates the position coordinate of a wall between each equipment room and an adjacent equipment room and a ceiling from the position coordinate data of each equipment room of a new facility stored in a memory device 2, and the generated data is saved in a memory device 5. Then, an operating means 6 determines the approximate shielded thickness of a wall between an equipment room and an adjacent equipment room, and ceiling thickness under study. Namely, one region (equipment room) A and an adjacent region B are read from an operating device 5, and the same combination as an adjoining relationship between the regions A and B are retrieved from existing facility design data in a memory device 1. The retrieved data of a wall between two regions and ceiling height in the existing facility are read out from the data of shielded wall thickness and ceiling thickness in the device 1, and the thickness is set and saved in a recording device 7 as the thickness of the wall between the regions A and B. Also, the building plan view data of the new facility saved in a memory device 3 and the position coordinate of the shielded wall and the ceiling in the device 5 are used to immediately display the required approximate dimensions on the screen of a display device 8.

6. 发明专利

JPH05134081A DIAGNOSING APPARATUS OF ABNORMALITY OF REACTOR 失效
公开(公告)号：JPH05134081A
公开(公告)日：1993-05-28
申请号：JP29695691
申请日：1991-11-13
申请人： TOSHIBA CORP
发明人： HAYASHIDA YOSHIHISA , HONMA HITOSHI
IPC分类号： G21C17/02
摘要： PURPOSE:To enable early specifying of a cooling system wherein breakdown of a heat transfer pipe occurs, by measuring a change in a dose rate by providing a radiation detector at a position whereat a secondary system main steam piping of each system is made to have a shielding effect. CONSTITUTION:The title apparatus comprises a dose rate measuring system 17 having radiation detectors 16 provided at positions which are located in the vicinity of secondary system main steam pipings 6 connecting steam generators 4 of a plurality of systems with a turbine 7, respectively, and whereat the pipings have a shielding effect for a radiation from pipings other than ones in the vicinity thereof, and an arithmetic device 18 which calculates a change in a dose rate by comparison with a normal state on the basis of data obtained from the measuring system 17 and can judge and specify the system wherein a leakage occurs, from the change in the dose detected by each radiation detector 16.

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