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1. 发明专利

JP2009230745A Method, program, and server for backup and restore 审中-公开
标题翻译：用于备份和恢复的方法，程序和服务器
公开(公告)号：JP2009230745A
公开(公告)日：2009-10-08
申请号：JP2009018620
申请日：2009-01-29
申请人： Toshiba Corp , Toshiba Solutions Corp , 東芝ソリューション株式会社 , 株式会社東芝
发明人： NOGUCHI MASANORI , KAIYA KAZUHIRO , KAWAKAMI YASUSHI , HOSAKA NORIKAZU , MATSUKAWA SHINICHI , KASAHARA AKIHIRO , MIURA AKIKAGE , MIYASHITA SHIGERU
IPC分类号： G06F12/00 , G06F21/24
CPC分类号： G06F21/10 , G06F11/1458 , G06F11/1469 , G06F21/6272 , G06F2221/2143 , G06F2221/2151 , H04L9/0822 , H04L9/0833 , H04L2209/60
摘要： PROBLEM TO BE SOLVED: To certainly prevent an illegal copy during the backup, restore and merge. SOLUTION: A recording device 16 (#a) which backs up a content α in a recording medium 18 and a recording device 16 (#b) which restores the content are registered in a server 12 so as to belong to the same domain group. When the recording device 16 (#b) attempts to restore the content, the restoration is permitted only when both the recording devices 16 belong to the same domain group. When there is a refresh request of the domain group, the domain group is invalidated only when a refresh period has elapsed. When a refresh number recorded in the recording device 16 (#a) is equal to or less than the refresh number recorded in the recording device 16 (#b), the recording device 16 (#b) can back up and can locally merge the content recorded in the recording device 16 (#a) into the recording medium. COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：为了在备份期间肯定防止非法复制，恢复和合并。解决方案：将记录介质18中的内容α备份的记录装置16（#a）和恢复内容的记录装置16（#b）登记在服务器12中以属于该记录装置域组。当记录装置16（#b）尝试恢复内容时，只有当两个记录装置16属于同一个域组时才允许恢复。当域组有刷新请求时，仅当刷新周期过去时，域组才会生效。当记录在记录装置16（#a）中的刷新号码等于或小于记录在记录装置16中的刷新号码（#b）时，记录装置16（#b）可以备份并且可以将记录在记录装置16（#a）中的内容进入记录介质。版权所有（C）2010，JPO＆INPIT

2. 发明专利

JP2008139321A Fuel assembly and core of nuclear reactor 审中-公开
标题翻译：燃料组装和核反应堆核心
公开(公告)号：JP2008139321A
公开(公告)日：2008-06-19
申请号：JP2007336811
申请日：2007-12-27
申请人： Toshiba Corp , 株式会社東芝
发明人： UEDA KIYOSHI , MIYASHITA SHIGERU , HAYASHI YAMATO , KAWASHIMA MASATOSHI
IPC分类号： G21C3/328 , G21C3/62
CPC分类号： Y02E30/38
摘要： PROBLEM TO BE SOLVED: To provide a core of a safe nuclear reactor of high conversion type or breeder type using light water or heavy water which does not use Na, such as light water reactors, and to provide a fuel assembly which can improve the utilization factor of nuclear fuels based on an improved method of the void coefficient with a new principle.
SOLUTION: The fuel assembly which employs light water or heavy water as the coolant and MOX fuel as the nuclear fuel material, and which is used for the nuclear reactor of high conversion type or breeder type of which moderator to fuel volume ratio is 1.0 or less, includes an upstream blanket 17 arranged at the lower end part, a downstream blanket 14 arranged at the upper end part, an upstream main exoergic part 16 and downstream main exoergic part 13 which are arranged between the upstream blanket 17 and downstream blanket 14 and have high Pu concentration, and a low concentration area 15 which is arranged between the upstream main exoergic part 16 and downstream main exoergic part 13 and has low Pu concentration.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：使用轻水或不使用Na的轻水（如轻水反应堆）提供高转化型或育种型安全核反应堆的核心，并提供一种燃料组件，其可以基于改进的空白系数方法，利用新的原理，提高核燃料的利用率。
解决方案：采用轻水或重水作为冷却剂的燃料组件和MOX燃料作为核燃料材料，用于具有调节剂与燃料体积比的高转化型或育种型核反应堆 1.0以下，包括布置在下端部的上游橡皮布17，布置在上端部的下游橡皮布14，设置在上游橡皮布17和下游橡皮布之间的上游主散热部16和下游主散热部13 14并具有高Pu浓度，以及低浓度区域15，其布置在上游主散热部分16和下游主散热部分13之间并具有低Pu浓度。版权所有（C）2008，JPO＆INPIT

3. 发明专利

JP2008131149A Content distribution system, content server, and program for content distribution 审中-公开
标题翻译：内容分发系统，内容服务器和内容分发程序
公开(公告)号：JP2008131149A
公开(公告)日：2008-06-05
申请号：JP2006311431
申请日：2006-11-17
申请人： Toshiba Corp , 株式会社東芝
发明人： UESONO SHIGEHIRO , MIYASHITA SHIGERU , KAKEHASHI HIDEKI , MOTOMATSU SEIJI
IPC分类号： H04L9/08 , H04N7/16 , H04N21/266
摘要： PROBLEM TO BE SOLVED: To provide a content distribution system, a content server, and a program for content distribution that enable a user to easily rent and view desired content data, namely, to view them only temporarily while preventing the user from illegally using the right etc.
SOLUTION: The content server 1 includes a user database 11a wherein recording medium unique information M
A as unique information of a recording medium 4 and user information as information associated with a user are related to each other, a ciphering unit 12a which reads the recording medium unique information M
A out of the user database 11a at requests from user terminals 21 to 2n and ciphers content key data Kc generated by ciphering content data C with the recording medium unique information M
A , and a first communication control unit 12b which transmit the ciphered content data Enc (Kc, C) and the ciphered content key data Enc (M
A , Kc) to the user terminals 21 to 2n.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：提供一种内容分发系统，内容服务器和用于内容分发的程序，其使得用户能够容易地租用和查看期望的内容数据，即仅在临时地查看它们，同时防止用户非法使用权利等。解决方案：内容服务器1包括用户数据库11a，其中作为记录介质4的唯一信息的记录介质唯一信息M SB A和/或作为与用户彼此相关;加密单元12a，其以用户终端21至2n的请求从用户数据库11a中读出记录介质唯一信息M SB，并且对通过加密产生的内容密钥数据进行加密具有记录介质唯一信息M 的内容数据C和发送加密内容数据Enc（Kc，C）和加密内容密钥数据Enc（M ）的第一通信控制单元12b， A ，Kc）发送给用户终端21至 2N。版权所有（C）2008，JPO＆INPIT

4. 发明专利

JP2007212482A Method for measuring infinite multiplication factor of reactor fuel 审中-公开
标题翻译：用于测量反应堆燃料的无穷多重因子的方法
公开(公告)号：JP2007212482A
公开(公告)日：2007-08-23
申请号：JP2007142662
申请日：2007-05-29
申请人： Toshiba Corp , 株式会社東芝
发明人： UEDA KIYOSHI , MIYASHITA SHIGERU , SASAKI TOMOHARU , MIHASHI TAKESHI , YOSHIOKA KENICHI
IPC分类号： G21C17/06
摘要： PROBLEM TO BE SOLVED: To nondestructively and accurately find the infinite multiplication factor of Pu fuel which is difficult to unseal. SOLUTION: A method is characterized in that the conversion ratio of a plutonium fuel rod is measured from a lateral face of it without unsealing a fuel rod containing plutonium and that the infinite multiplication factor of a plutonium fuel rod cell is found by using the conversion ratio of the plutonium fuel rod obtained by the measurement, the fission rate of Pu239, the capture rate of Pu239 and the physical multiplier of Pu239. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：非破坏性地准确地找到难以开封的Pu燃料的无限倍增因子。解决方案：一种方法的特征在于，钚燃料棒的转化率从其侧面测量而不开封含有钚的燃料棒，并且通过使用钚燃料棒电池的无限倍增因子通过测量获得的钚燃料棒的转化率，Pu239的裂变率，Pu239的捕获率和Pu239的物理乘数。版权所有（C）2007，JPO＆INPIT

5. 发明专利

JP2000221293A DEVICE AND METHOD FOR MEASURING BURNUP OF FUEL FOR NUCLEAR REACTOR 失效
公开(公告)号：JP2000221293A
公开(公告)日：2000-08-11
申请号：JP2097499
申请日：1999-01-29
申请人： TOSHIBA CORP
发明人： YOSHIOKA KENICHI , MIYASHITA SHIGERU
IPC分类号： G21C17/06
摘要： PROBLEM TO BE SOLVED: To take an appropriate measurement of gamma rays of a fission product and capture gamma rays from a fuel for a nuclear reactor and realize a simple and highly reliable measuretnent of burnup. SOLUTION: This device includes a gamma-ray detector 2 that is adjacent to a fuel 1 for a nuclear reactor, is placed in the water and measures the intensity of capture gamma rays of neutrons and gamma rays of a fission product, a gamma-ray shield 7 that is located between the gamma-ray detector 2 and the fuel 1 and spectrum collecting means 10 and 11 that are connected with the gamma-ray detector 2 and collect gamma-ray spectra.

6. 发明专利

JP2000258582A MEASURING METHOD FOR INFINITE MULTIPLICATION FACTOR OF REACTOR FUEL 失效
公开(公告)号：JP2000258582A
公开(公告)日：2000-09-22
申请号：JP5644699
申请日：1999-03-04
申请人： TOSHIBA CORP
发明人： UEDA KIYOSHI , MIYASHITA SHIGERU , SASAKI TOMOHARU , MIHASHI TAKESHI , YOSHIOKA KENICHI
IPC分类号： G21C17/00 , G21C17/06
摘要： PROBLEM TO BE SOLVED: To obtain non-destructively and accurately the infinite multiplication factor of Pu fuel which is hardly opened. SOLUTION: Without opening the seal of Pu fuel rods, a conversion ratio is measured from the side and the conversion ratio obtained with this measurement is used to obtain, an infinite multiplication factor of a Pu fuel rod cell. At this moment, the ratio of finite multiplication factor of the Pu fuel rod cell at a position to be measured in a fuel lattice and multiplication factor of the Pu fuel rod itself in a thermal neutron field is obtained as a first factor and the infinite multiplication factor of plutonium fuel rod itself in the thermal neutron field is obtained by operation as a second factor. It is desired to obtain the infinite multiplication factor of Pu fuel rod cell at the position to be measured by the product of the first factor and the second factor.

7. 发明专利

JPH0755990A EVALUATION METHOD FOR CONTROL ROD NUCLEAR LIFE 失效
公开(公告)号：JPH0755990A
公开(公告)日：1995-03-03
申请号：JP20160693
申请日：1993-08-13
申请人： TOSHIBA CORP
发明人： UEDA KIYOSHI , MIHASHI EIJI , KUMANOMIDOU HIRONORI , MIYASHITA SHIGERU , SASAKI TOMOHARU , KIKUCHI TSUKASA
IPC分类号： G01N23/09 , G21C7/08 , G21C17/10
摘要： PURPOSE:To evaluate the nuclear life for an advanced control rod for typical example of hafnium (Hf). CONSTITUTION:An unused non-irradiated control rod or a simulated control rod simulating the main part of it is set as a reference control rod with known components. A calibration curve is made from the neutron transmittance, burnup dependent transmittance and burnup dependent reactivity to this reference control rod and the reactivity of an irradiated control rod is evaluated from the calibration curve and the neutron transmittance in the irradiated control rod. And the nuclear life of the irradiated control rod is evaluated from the relation between reactivity reduction rate accompanied by irradiation determined independently and life.

8. 发明专利

JP2000241582A FUEL ASSEMBLY, FUEL ROD AND REACTOR CORE 失效
公开(公告)号：JP2000241582A
公开(公告)日：2000-09-08
申请号：JP3908499
申请日：1999-02-17
申请人： TOSHIBA CORP
发明人： UEDA KIYOSHI , MIYASHITA SHIGERU , HAYASHI YAMATO , KAWASHIMA MASATOSHI
IPC分类号： G21C3/06 , G21C3/16 , G21C3/17 , G21C3/28 , G21C3/324 , G21C3/326 , G21C3/328 , G21C7/00 , G21C7/06
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly, fuel rods and a reactor core for using MOX based on a new principle improving void coefficient. SOLUTION: A fuel assembly 1 is constituted, from the upstream to the downstream, of an upstream side blanket 17, an upstream side main heated region 16, a low concentration region 15, a downstream side main heated region 13 and a downstream side blanket 14. In the downstream side blanket 14, a low scattering space 6 and a moderator and coolant space are provided. When the void coefficient of the coolant rises, neutron moving area (distance) increases and the dispersed absorber segments can absorb neutrons in longer distance. On the other hand, the absorbing ability of the absorber segment is saturation type and does not reduce even with hardening of neutron spectrum and so the absorbing ability eventually increases and the void coefficient can be improved in negative direction.

9. 发明专利

JPH0990080A CONTROL ROD FOR REACTOR 失效
公开(公告)号：JPH0990080A
公开(公告)日：1997-04-04
申请号：JP24966595
申请日：1995-09-27
申请人： TOSHIBA CORP
发明人： MIYASHITA SHIGERU , UEDA KIYOSHI
IPC分类号： G21C7/10 , G21C7/113 , G21C7/24
摘要： PROBLEM TO BE SOLVED: To reduce reactivity worth automatically during reactor operation and increase the reactivity worth automatically during reactor shutdown. SOLUTION: A box shape blade 18a is constituted of a (n, γ) reaction type neutron absorber 21 containing hafnium at least in a part of neutron absorber. In this box shape blade 18a, a water path hole 24 set in the size that reactor water boiling in the box shape blade 18a is exhausted from interior by γ heat- generation of the neutron absorber 21 during operation, is punched.

10. 发明专利

JPH0511085A FUEL ASSEMBLY FOR BOILING WATER REACTOR 失效
公开(公告)号：JPH0511085A
公开(公告)日：1993-01-19
申请号：JP16135991
申请日：1991-07-02
申请人： TOSHIBA CORP
发明人： MIYASHITA SHIGERU , UEDA KIYOSHI
IPC分类号： G21C3/326
摘要： PURPOSE:To reduce the neutron flux radiating from a spent fuel assembly and improve the criticality safety for storage by enabling water rod to separate into upper and lower parts and providing inside neutron absorber by insertion. CONSTITUTION:A combined neutron absorber 11 is constituted of a neutron absorber material 12 such as boron having an outer shape of rod and capable of inserting in a water rod 2 and a upper tieplate 13 with a handle 4 above it which is fixed in one with a nat 14. The upper tieplate 5 and the upper water rod 8 are lifted up for removal from a spent fuel assembly 1. The neutron absorber 11 combined with the upper tieplate is inserted in the lower water rod 9 in the spent fuel assembly and fixed to a part of the fuel rods 3 with a nat. By this, it becomes possible to reduce neutron flux and increase the subcriticality in the assembly 1 and improve the capacity efficiency for storage.

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