公开(公告)号：JP2006292540A

公开(公告)日：2006-10-26

申请号：JP2005113383

申请日：2005-04-11

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  核燃料サイクル開発機構

Inventor： GUNJI MINORU ,  KATAOKA HAJIME

IPC: G01P13/00 ,  G01W1/02

Abstract: PROBLEM TO BE SOLVED: To provide an anemometer manufactured inexpensively and easily at a working level using only a material available easily, while allowing a wind velocity and a wind direction to be measured relatively precisely.
SOLUTION: This anemometer is provided with a vane fixing plate 1 turned to direct a tip part windwards, a support part 2 for supporting turnably the vane fixing plate 1, a pair of openable and closable vanes 3a, 3b attached to both faces of the vane fixing plate 1, and a plurality of permanent magnets 4 for imparting resiliency along a direction of opening the vanes 3a, 3b. The pair of vanes 3a, 3b is brought into a stationary condition in a position balanced with closing force due to push of wind when receiving the wind and the resiliency of the permanent magnets 4, and the wind velocity is specified based on a stationary position.
COPYRIGHT: (C)2007,JPO&INPIT

Abstract translation: 要解决的问题：提供一种仅使用容易获得的材料在工作水平上廉价且容易地制造的风速计，同时允许相对精确地测量风速和风向。 解决方案：该风速计设置有转向使尖端部分向上引导的叶片固定板1，用于可转动地支撑叶片固定板1的支撑部分2，附接到两个面的一对可开启和关闭的叶片3a，3b 和用于沿着打开叶片3a，3b的方向赋予弹性的多个永久磁铁4。 一对叶片3a，3b在受到风的推动和永久磁铁4的弹性的作用下，在与闭合力平衡的位置处于静止状态，并且基于静止位置指定风速。 版权所有（C）2007，JPO＆INPIT

公开(公告)号：JP2006275795A

公开(公告)日：2006-10-12

申请号：JP2005095881

申请日：2005-03-29

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  Nippon Nuclear Fuel Dev Co Ltd ,  Toshiba Corp ,  日本核燃料開発株式会社 ,  株式会社東芝 ,  核燃料サイクル開発機構

Inventor： TSUBOI YASUSHI ,  ISHII TETSUYA ,  YUDA RYOICHI

IPC: G21C3/62

CPC classification number: Y02E30/34 ,  Y02E30/38

Abstract: PROBLEM TO BE SOLVED: To provide a nuclear fuel pellet not requiring a heat-treatment process after sintering of the pellet by regulating the amount of metal uranium (U) granules added to an oxide powder being a raw material powder, to control the O/M ratio of the sintered pellet to a value lower than the value in the conventional case, and also to provide its manufacturing method. SOLUTION: The manufacturing method for the nuclear fuel pellet comprises the steps of: adding the metal uranium particles of a required equivalent spherical diameter to the oxide powder containing a nuclear fuel substance and mixing them; compressing and molding the mixed oxide powder to make a green pellet; and sintering the green pellet thus yielded at a specified temperature for a specified time in a sintering furnace having an inert gas atmosphere. COPYRIGHT: (C)2007,JPO&INPIT

Abstract translation: 要解决的问题：提供一种不需要热处理工艺的核燃料颗粒，其通过调节加入到作为原料粉末的氧化物粉末中的金属铀（U）颗粒的量来烧结后，控制 烧结颗粒的O / M比低于常规情况下的值，并且提供其制造方法。 解决方案：核燃料颗粒的制造方法包括以下步骤：将所需等效球形直径的金属铀颗粒加入含有核燃料物质的氧化物粉末并混合; 压缩和模塑混合氧化物粉末以制成绿色颗粒; 并在具有惰性气体气氛的烧结炉中烧结生成的颗粒，使其在规定温度下规定时间。 版权所有（C）2007，JPO＆INPIT

公开(公告)号：JP2006048579A

公开(公告)日：2006-02-16

申请号：JP2004232073

申请日：2004-08-09

Applicant: Image Partner:Kk ,  Japan Nuclear Cycle Development Inst States Of Projects ,  株式会社イメ−ジパ−トナ− ,  核燃料サイクル開発機構

Inventor： TAKAHASHI KATSUHIKO ,  HIKIMA TAKAFUMI ,  YAMAMOTO YUZO ,  HIDA KAZUNORI

IPC: G08B27/00 ,  H04M11/04

CPC classification number: H04M3/42 ,  G08B25/14 ,  H04M1/2745 ,  H04M2242/04

Abstract: PROBLEM TO BE SOLVED: To provide an emergency call panel that enables quick and easy control of an emergency call server of an emergency communications system, by readily operating buttons and to provide an emergency communication system that comprises the emergency call server and the emergency call panel.
SOLUTION: The emergency call panel has a report button that can be initially allocated, corresponding to a standard report given by the call server of the emergency communication system, and a transmission button for transmitting data on the selected standard report to the call server, while the report button is selected according to the standard report. The emergency communication system comprises the call server and the emergency call panel for executing the report process of the call server. On the emergency call panel, the report button, corresponding to the standard report is selected according to the content of a report and start request data including data on the standard report selected are sent to the call server. When the call server obtains the start request data, a reporting process is executed.
COPYRIGHT: (C)2006,JPO&NCIPI

Abstract translation: 要解决的问题：提供一种紧急呼叫面板，其能够通过容易地操作按钮并且提供包括紧急呼叫服务器和紧急呼叫服务器的紧急通信系统来实现对紧急通信系统的紧急呼叫服务器的快速和容易的控制， 紧急呼叫面板

解决方案：紧急呼叫面板具有可以初始分配的报告按钮，对应于紧急通信系统的呼叫服务器给出的标准报告，以及用于将所选择的标准报告上的数据发送到呼叫的传输按钮 服务器，同时根据标准报告选择报告按钮。 紧急通信系统包括呼叫服务器和用于执行呼叫服务器的报告处理的紧急呼叫面板。 在紧急呼叫面板上，根据报告内容选择与标准报告相对应的报告按钮，包括所选标准报告数据的启动请求数据发送到呼叫服务器。 当呼叫服务器获取开始请求数据时，执行报告处理。 版权所有（C）2006，JPO＆NCIPI

公开(公告)号：JP2006030001A

公开(公告)日：2006-02-02

申请号：JP2004209621

申请日：2004-07-16

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  核燃料サイクル開発機構

Inventor： IKEGAMI TETSUO

IPC: G21C19/44 ,  G21C3/328 ,  G21C3/62 ,  G21C5/18 ,  G21C19/34

CPC classification number: Y02E30/34 ,  Y02E30/38 ,  Y02W30/881 ,  Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To enable the multiple uses of fuel spent in a light water reactors only by conducting recovery treatment involving a simple heat treatment and the reusable fuel processing. SOLUTION: Fuel 1 spent in the light water reactor is extracted from cladding tubes for the light water reactor by recovery treatment involving a simple heat treatment (SP1) and is made reusable fuel by reusable fuel manufacturing (reusable fuel processing; SP2) and the reusable fuel is filled and loaded into cladding tubes for a fast reactor. Additionally, the reusable fuel in the cladding tubes in the fast reactor loaded into them is characterized in that it is made reusable fuel again by being extracted from the cladding tubes for the fast reactor through the recovery treatment involving the simple heat treatment (SP1) and by the reusable fuel manufacturing (SP2) at intervals of a recycle time set within the allowable durability period for the cladding tubes for the fast reactor in it and that the reloading into the fast reactor--the loading into it by filling the reusable fuel into new cladding tubes for the fast reactor--is repeated once or more. COPYRIGHT: (C)2006,JPO&NCIPI

Abstract translation: 要解决的问题：为了能够通过进行简单的热处理和可重复使用的燃料处理的回收处理，能够在轻水反应堆中多次使用燃料。 解决方案：通过涉及简单热处理（SP1）的回收处理，在轻水反应堆的包覆管中提取燃料1，并通过可重复使用的燃料制造（可重复使用的燃料处理; SP2）制成可重复使用的燃料， 并且将可重复使用的燃料填充并装载到用于快速反应器的包层管中。 此外，装载在其中的快速反应堆中的包层管中的可重复使用的燃料的特征在于，通过通过简单热处理（SP1）的回收处理从用于快堆的包层管中提取可再生燃料， 通过可重复使用的燃料制造（SP2），间隔时间设定在其中用于其中的快速反应堆的包壳管的允许耐久期内，并且重新加载到快速反应堆中 - 通过将可重复使用的燃料装入 用于快速反应堆的新型包覆管 - 重复一次或多次。 版权所有（C）2006，JPO＆NCIPI

公开(公告)号：JP2006010356A

公开(公告)日：2006-01-12

申请号：JP2004184237

申请日：2004-06-22

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  核燃料サイクル開発機構

Inventor： HARADA HIDEO ,  SHCHERBAKOV OLEG ALEXEEVICH

IPC: G01N23/09 ,  G01T1/34 ,  G01T1/36 ,  G01T3/00 ,  G21C17/06 ,  G21K5/02 ,  G21K5/08

Abstract: PROBLEM TO BE SOLVED: To identify a nuclide to determinate its content. SOLUTION: A sample 18 to be analyzed is irradiated with pulse neutrons from an external neutron source and the energy distribution of transmitted neutrons is detected by a neutron detector 22 while the cavity of a neutron resonance peak at every nuclide is observed by a flying time measuring method not only to identify the nuclide contained in the sample but also to determinate its content. The sample to be analyzed is placed on an unidimensional or two-dimensional sample drive stand 16 and moved to be irradiated with collimated pulse neutrons and the transmitted neutrons are measured by the neutron detector while a background is removed by a shield body. By this method, the kind of the nuclide contained in the sample and the position dependency of the content of the nuclide can be calculated. COPYRIGHT: (C)2006,JPO&NCIPI

Abstract translation: 要解决的问题：确定核素以确定其内容。 解决方案：待分析的样品18用来自外部中子源的脉冲中子照射，并且透射中子的能量分布由中子检测器22检测，而每个核素的中子共振峰的空腔被观察到 飞行时间测量方法不仅可以识别样品中包含的核素，而且可以确定其含量。 要分析的样品放置在一维或二维采样驱动支架16上，并移动以用准直脉冲中子照射，并且通过中子探测器测量透射的中子，同时通过屏蔽体去除背景。 通过该方法，可以计算样品中所含的核素种类和核素含量的位置依赖性。 版权所有（C）2006，JPO＆NCIPI

公开(公告)号：JP2006010355A

公开(公告)日：2006-01-12

申请号：JP2004184212

申请日：2004-06-22

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  Koatsu System Kk ,  核燃料サイクル開発機構 ,  高圧システム株式会社

Inventor： ICHIKAWA SHOICHI ,  ABE YASUHIRO ,  ENDO TOSHIAKI ,  OMORI TAKESHI ,  KOJIMA YASUTOSHI ,  OKAZAWA HIROSHI

IPC: G21C23/00 ,  G01N1/28 ,  G01N3/00

CPC classification number: Y02E30/40

Abstract: PROBLEM TO BE SOLVED: To reduce much waste of tagging gas and reduce the manufacturing cost of an internal pressure creep test piece by uniformly mixing the tagging gas and internal pressure loading gas, exactly grasping their mixing fractions and exactly calculating internal stress at high temperature.
SOLUTION: The internal pressure creep test piece 24 is placed in enclosure vessels 10, 12, the tag gas and internal pressure loading gas are introduced into the enclosure vessels and filled in the internal pressure creep test piece, and a gas introducing hole of the internal pressure creep test piece is sealed with laser welding. Here, in the front step of the enclosure vessel, a mixer 14 which is provided with a stirring function and variable inner volume is placed. The tagging gas and the internal pressure loading gas are separately introduced in the mixer and high pressure mixture gas is compressed into the enclosure vessel by a plunger for injecting in a mixing room.
COPYRIGHT: (C)2006,JPO&NCIPI

Abstract translation: 要解决的问题：为了减少标签气体的大量浪费，并通过均匀混合标记气体和内部加压气体来降低内部压力蠕变试验片的制造成本，精确掌握其混合分数并精确计算内部应力 高温。 解决方案：将内部压力蠕变试验片24放置在封闭容器10,12中，将标签气体和内部加压气体引入到封闭容器中并填充在内部压力蠕变试验片中，并将气体导入孔 的内部压力蠕变试验片用激光焊接密封。 这里，在封闭容器的前台阶段，设置具有搅拌功能和可变内容积的混合器14。 标记气体和内部加压气体分别引入混合器中，高压混合气体通过用于注入混合室的柱塞压缩到封闭容器中。 版权所有（C）2006，JPO＆NCIPI

公开(公告)号：JP2005257524A

公开(公告)日：2005-09-22

申请号：JP2004070639

申请日：2004-03-12

Applicant: Aloka Co Ltd ,  Japan Nuclear Cycle Development Inst States Of Projects ,  アロカ株式会社 ,  核燃料サイクル開発機構

Inventor： TSUJIMURA NORIO ,  YAMANO TOSHIYA

IPC: G01T3/00 ,  G01T1/20

Abstract: PROBLEM TO BE SOLVED: To realize a radiation measurement system which has a good mobility at an actual measurement and executes the measurement with good accuracy. SOLUTION: A neutron measurement system is composed of a surveymeter 10, an auxiliary measurement device 12 and a system controller 14. In a calibration process carried out by a prior measurement, the content of relational expression contained in the surveymeter 10 is compensated by using count values of the auxiliary measurement device 12. The relational expression includes an energy estimation function and a conversion factor decision function. After compensating the relational expression appropriately, neutrons are actually measured by utilizing the surveymeter alone. Thus, the relational expression is compensated in accordance with an actual field of neutrons, and the actual measurement is precisely carried out by using the surveymeter 10. COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：实现在实际测量中具有良好移动性的辐射测量系统，并以高精度执行测量。 解决方案：中子测量系统由测量计10，辅助测量装置12和系统控制器14组成。在通过先前的测量执行的校准过程中，包含在测量计10中的关系表达式的内容被补偿 通过使用辅助测量装置12的计数值。关系表达式包括能量估计函数和转换因子决定函数。 在适当地补偿关系表达式之后，实际上通过单独使用测量计来测量中子。 因此，根据中子的实际领域来补偿关系表达式，并且通过使用测量计10精确地进行实际测量。（C）2005年，JPO和NCIPI

公开(公告)号：JP2005221434A

公开(公告)日：2005-08-18

申请号：JP2004031205

申请日：2004-02-06

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  Nagaaki Satou ,  修彰 佐藤 ,  核燃料サイクル開発機構

Inventor： SATO SOICHI ,  SATOU NAGAAKI

IPC: G21C19/44

CPC classification number: Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To make it possible to separate fuel substances from other nuclear fission products without dissolving the substances as they remain oxides. SOLUTION: This method includes (1) a pulverization process for pulverizing fuel elements by heating and oxidizing spent fuel, (2) a selective sulfurization process for reducing the fuel substances and selectively sulfurizing nuclear fission products into sulfide or oxysulfide by heating the pulverulent bodies obtained in the pulverization process in an atmosphere containing a sulfurizer and (3) a partial dissolution process for dissolving the sulfide by washing substances obtained in the selective sulfurization process with a dilute acid to wash away the nuclear fission product elements and extracting the fuel substances as oxides. COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：为了使燃料物质与其他核裂变产物分离而不会在物质保留氧化物时溶解，可能会有可能。 解决方案：该方法包括（1）通过加热和氧化废燃料来粉碎燃料元件的粉碎过程，（2）选择性硫化方法，用于减少燃料物质，并通过加热将核裂变产物选择性硫化成硫化物或硫化硫 在含有硫化剂的气氛中在粉碎过程中获得的粉状体和（3）通过用稀酸洗涤在选择性硫化过程中获得的物质来溶解硫化物的部分溶解过程，以洗涤核裂变产物元素并提取燃料 物质作为氧化物。 版权所有（C）2005，JPO＆NCIPI

公开(公告)号：JP2005172428A

公开(公告)日：2005-06-30

申请号：JP2003408026

申请日：2003-12-05

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  核燃料サイクル開発機構

Inventor： HOSHIYA TAIJI

IPC: G01N17/00 ,  G01N23/00 ,  G21B1/11 ,  G21B1/17

CPC classification number: G01N33/20

Abstract: PROBLEM TO BE SOLVED: To determine a using condition of a material under an irradiation environment at low cost in a short time, in application to the irradiation environment of the new material represented by ordered structure alloy or the like.
SOLUTION: A condition-under-irradiation diagram for expressing a relationship of a long range regularity degree to a condition-under-irradiation variable R as to an irradiation velocity and a temperature is created in response to ordered structure of the alloy, based on an evaluation expression as to an irradiation effect affecting a condition under irradiation, using as parameters a first threshold where the degree of regularity starts to go remarkably down under the irradiation environment, a second threshold reaching to substantial equilibrium after the going-down, and an equilibrium long range regularity degree. An R value under a planed using irradiation condition about the determined alloy is calculated to find a long range regularity degree S corresponding thereto, the first threshold, the second threshold and the equilibrium long range regularity degree are found in the same R value to be compared, and a degree of damage and a fluctuation situation thereof are predicted thereby to determine the service condition.
COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：为了在短时间内以低成本在照射环境下确定材料的使用条件，适用于由有序结构合金等表示的新材料的照射环境。 解决方案：响应于合金的有序结构，产生用于表示关于照射速度和温度的长距离规则度与照射条件条件R的关系的条件照射下条件， 基于影响照射条件的照射效果的评价表达，使用在照射环境下规则性开始显着下降的第一阈值作为参数，在下降后达到实质平衡的第二阈值， 和平衡长程规律度。 计算使用关于所确定的合金的照射条件下的R值，以找到与其对应的长距离规则度S，在相同的R值中找到第一阈值，第二阈值和平衡长程规律度，以进行比较 并且预测其损伤程度和波动状况，从而确定使用条件。 版权所有（C）2005，JPO＆NCIPI

公开(公告)号：JP2005140791A

公开(公告)日：2005-06-02

申请号：JP2004337731

申请日：2004-11-22

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  核燃料サイクル開発機構

Inventor： HIRABAYASHI MASARU ,  ARA KUNIAKI ,  HAYASHIDA HITOSHI

IPC: G01N23/04 ,  F22B37/02 ,  G21C17/003

Abstract: PROBLEM TO BE SOLVED: To easily and nondestructively perform inspection on defects or wall thickness by imaging a cross section of a heat transfer tube group under inspection irrespective of the material quality and structure of each heat transfer tube or the arranged state, etc. of a multitude of heat transfer tubes.
SOLUTION: This heat transfer tube group inspection device is equipped with: radiation sources 16 installed in any one or more places inside a heat transfer tube 12, inside the heat transfer tube group 10, and outside the tube group; a radiation detector 18 fitted with a collimator 20 installed so as to make it possible to detect radiation emitted from the radiation sources outside the tube group all over the circumference thereof; and a CT processor 22 for CT-processing intensity signals on the radiation detected by the radiation detector. The cross-sections of the tube group comprising a multitude of arranged heat transfer tubes are imaged by means of the CT processing, thereby nondestructively inspecting the tube group.
COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：通过对检查中的传热管组的横截面进行成像来容易且无损地执行缺陷或壁厚的检查，而不管每个传热管的材料质量和结构或布置状态等。 的大量传热管。 解决方案：该传热管组检查装置配备有：放射源16，其安装在传热管12的内部，传热管组10内部和管组外部的任何一个或多个位置; 安装有准直仪20的放射线检测器18，以便能够在其整个圆周上检测从管组外部的辐射源发射的辐射; 以及CT处理器22，用于对辐射检测器检测到的辐射进行CT处理强度信号。 包括多个布置的传热管的管组的横截面通过CT处理成像，从而非破坏性地检查管组。 版权所有（C）2005，JPO＆NCIPI