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    廃棄物処理のための方法及び装置
    22.
    发明专利
    廃棄物処理のための方法及び装置 审中-公开

    公开(公告)号：JP2018119960A

    公开(公告)日：2018-08-02

    申请号：JP2018005134

    申请日：2018-01-16

    Applicant: ズガルジー,アンドレア ,  SGARGI,Andrea

    Inventor： ズガルジー,アンドレア

    IPC: G21F9/36 ,  G21F9/02 ,  G21F9/30 ,  G21F9/32

    CPC classification number: G21F9/32 ,  B01D53/14 ,  B01D2252/103 ,  G21F9/02 ,  G21Y2002/60 ,  G21Y2004/20 ,  G21Y2004/201

    Abstract: 【課題】放射性物質の大部分の効果的な廃棄を承諾するのに適した廃棄物処理のための方法及び装置を得ること。 【解決手段】廃棄物を処理するための方法が提供され、廃棄物2が放射性廃棄物であり、方法は、処理前廃棄物2aが熱分解反応器3内に配置される第1のステップと、処理前廃棄物が熱分解によって処理済み廃棄物4へと熱的に分解される第2のステップとを備え、処理済み廃棄物が固相40と気相41とを備え、また、方法は、固相が既知の放射性廃棄物貯蔵手順にしたがって貯蔵される第3のステップと、気相が外部環境へと放出される第4のステップとを備える。 【選択図】図1

    Lwr flow channel whose deformability and control blade coherence are lowered when it is exposed to neutron radiation and corrosion field
    23.
    发明专利
    Lwr flow channel whose deformability and control blade coherence are lowered when it is exposed to neutron radiation and corrosion field 审中-公开
    LWR流量通道在暴露于中子辐射和腐蚀现场时，可变性和控制叶片的相关性降低

    公开(公告)号：JP2007192814A

    公开(公告)日：2007-08-02

    申请号：JP2006349436

    申请日：2006-12-26

    Applicant: General Electric Co ,  ゼネラル・エレクトリック・カンパニイGeneral Electric Company

    Inventor： LUTZ DANIEL REESE ,  POTTS GERALD ALLEN ,  LIN YANG-PI ,  MAHMOOD SHEIKH TAHIR ,  DUBECKY MARK ANDREW ,  WHITE DAVID WILLIIAM ,  SCHARDT JOHN

    IPC: G21C3/324 ,  G21C3/30 ,  G21C5/00 ,  G21D1/00

    CPC classification number: G21C3/07 ,  G21C3/324 ,  G21Y2002/203 ,  G21Y2002/207 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: PROBLEM TO BE SOLVED: To provide zircaloy suitable for forming reactor components which shows a decrease in irradiation growth and the improvement in corrosion resistance during the operation of a light water reactor (LWR) such as a boiling water reactor (BWR).
    SOLUTION: During the operation of a reactor, the reactor components are exposed to an irradiation field which is intense enough to induce or accelerate the corrosion on an alloy face irradiated inside a core and is asymmetrical in most cases. Moreover, the reactor components manufactured from the disclosed zircaloy tend to show the improvement also in an aspect of the allowance to the cold working during the manufacture of the components. Therefore, the reduction or no implementation of the thermal treatment, such as annealing, conducted following the cold working facilitates the manufacture of such reactor components and also eliminates the excessive deterioration in the performance of the components after the completion of them.
    COPYRIGHT: (C)2007,JPO&INPIT

    Abstract translation: 要解决的问题：提供适用于形成反应器组分的氧化锆，其显示出在诸如沸水反应器（BWR）的轻水反应器（LWR）的操作期间照射生长减少和耐腐蚀性的改善。 解决方案：在反应器操作期间，反应器部件暴露于强度足以引起或加速在芯内照射的合金面上的腐蚀的照射场，并且在大多数情况下是不对称的。 此外，由公开的氧化锆制造的反应器部件在组件的制造过程中在冷加工余量的一个方面也趋于改善。 因此，在冷加工之后进行的退火等的热处理的还原或不实施有助于制造这种反应器部件，并且还消除了在完成部件后的性能的过度劣化。 版权所有（C）2007，JPO＆INPIT

    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method
    26.
    发明授权
    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method 失效
    表面处理反应器构件的方法和使用表面处理方法制造反应器构件的方法

    公开(公告)号：US06869338B2

    公开(公告)日：2005-03-22

    申请号：US10190517

    申请日：2002-07-09

    Applicant: Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    IPC: G21C21/00 ,  G21C3/07 ,  G21C3/12 ,  G21C3/33 ,  B24B1/00

    CPC classification number: G21C3/07 ,  G21C3/12 ,  G21Y2002/103 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40 ,  Y10S148/908 ,  Y10S376/90

    Abstract: A method of surface-treating a reactor member for effectively removing a Cr-deficient layer and a work-hardened layer considered to be a cause of stress-corrosion cracking (SCC) under low-stress conditions. The method of surface-treating a reactor member which is worked by bending (step 1) and then processed by a heat treatment (step 2), in which a work-hardened layer is formed by the bending, and in which a Cr-deficient layer is formed due to an oxide film attached by the heat treatment, uses at least one of: acid wash; grinding; electrolytic polishing; electro-discharge machining; surface cutting; surface deoxidation and softening; wet blasting; laser machining; or surface plating (step 3) to remove the work-hardened layer and the Cr-deficient layer from the reactor member or to prevent contact of the work-hardened layer and the Cr-deficient layer of the reactor member with a primary coolant.

    Abstract translation: 在低应力条件下，有效去除Cr缺陷层和被认为是应力腐蚀开裂原因（SCC）的加固硬化层的反应器构件的表面处理方法。 表面处理通过弯曲（步骤1）进行加工，然后通过热处理（步骤2）进行加工的反应器构件的表面处理方法，其中通过弯曲形成加工硬化层，并且其中Cr缺陷 由于通过热处理而附着的氧化膜形成层，使用以下中的至少一种：酸洗; 研磨 电解抛光; 放电加工; 表面切割; 表面脱氧和软化; 湿喷 激光加工; 或表面电镀（步骤3）以从反应器构件去除加固硬化层和Cr缺陷层，或者防止加固硬化层和反应器构件的Cr缺陷层与初级冷却剂接触。

    Zirconium-base alloy and nuclear reactor component comprising the same
    27.
    发明授权
    Zirconium-base alloy and nuclear reactor component comprising the same 失效
    锆基合金和包含其的核反应堆组分

    公开(公告)号：US06690759B1

    公开(公告)日：2004-02-10

    申请号：US10263714

    申请日：2002-10-04

    Applicant: Shuichi Nanikawa ,  Shinji Ishimoto ,  Toshio Kubo

    Inventor： Shuichi Nanikawa ,  Shinji Ishimoto ,  Toshio Kubo

    IPC: G21C307

    CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C1/084 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: Disclosed herein are zirconium-base alloys excellent in both corrosion resistance and hydrogen absorption property, useful as materials for nuclear reactors. Such a zirconium-base alloy for nuclear reactors comprises 0.5-2 wt. % Sn, 0.07-0.6 wt. % Fe, 0.03-0.2 wt. % Ni, 0.05-0.2 wt. % Cr, and the balance being zirconium and unavoidable impurities, wherein the Fe content (X wt. %) of the zirconium-base alloy and the mean size (Y nm) of precipitates in the zirconium-base alloy are present in a region on the x (Fe content X) and y (mean precipitate size) rectangular coordinates, surrounded by the following five lines: i) Y=−444×X+154, ii) Y=910×X−46, iii) Y=0, iv) Y=300, and v) X=0.6.

    Abstract translation: 本文公开了耐腐蚀性和吸氢性优异的锆基合金，可用作核反应堆的材料。 这种用于核反应堆的锆基合金包含0.5-2wt。 ％Sn，0.07-0.6重量％ ％Fe，0.03-0.2重量％ ％Ni，0.05-0.2重量％ ％Cr，余量为锆和不可避免的杂质，其中锆基合金的Fe含量（X重量％）和锆基合金中析出物的平均粒径（Ynm）存在于 由以下五行包围的x（Fe含量X）和y（平均沉淀物大小）直角坐标：i）Y = -444xX + 154，ii）Y = 910xX-46，iii）Y = 0，iv）Y = 300，v）X = 0.6。

    Nuclear reaction fuel assembly for a nuclear reactor fuel assembly
    28.
    发明授权
    Nuclear reaction fuel assembly for a nuclear reactor fuel assembly 有权
    核反应堆燃料组件的核反应燃料组件

    公开(公告)号：US6154514A

    公开(公告)日：2000-11-28

    申请号：US132475

    申请日：1998-08-11

    Applicant: Kazuo Murakami ,  Shinichi Shiraishi ,  Kiyoshi Izumi

    Inventor： Kazuo Murakami ,  Shinichi Shiraishi ,  Kiyoshi Izumi

    IPC: G21C3/33 ,  G21C3/12 ,  G21C19/06

    CPC classification number: G21C3/12 ,  G21Y2002/104 ,  G21Y2004/201 ,  G21Y2004/305 ,  Y02E30/40

    Abstract: An upper hold-down spring structure for a nuclear reactor fuel assembly. A hold down spring 20 mounted on an upper surface of an upper nozzle 11 of a fuel assembly for a pressurized water reactor is composed of an upper plate spring 21 having plastic spring characteristics and a lower plate spring 23, base ends of which are fixed with a fastening bolt 18 at a common position. The upper spring 21 and the lower spring 23 are made of precipitation hardened nickel base alloy and the thickness of the springs are determined so as to keep the stresses generated less sensitive to stress corrosion cracking.

    Abstract translation: 用于核反应堆燃料组件的上压紧弹簧结构。 安装在用于压水反应堆的燃料组件的上喷嘴11的上表面上的按压弹簧20由具有塑料弹簧特性的上板簧21和下板弹簧23组成，底板弹簧21的基端固定有 在同一位置的紧固螺栓18。 上弹簧21和下弹簧23由沉淀硬化的镍基合金制成，并且弹簧的厚度被确定为保持对应力腐蚀开裂不敏感的应力。

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