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公开(公告)号：US11574746B2
公开(公告)日：2023-02-07
申请号：US17081976
申请日：2020-10-27
申请人： TerraPower, LLC
摘要： A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.
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公开(公告)号：US20210210223A1
公开(公告)日：2021-07-08
申请号：US17081976
申请日：2020-10-27
申请人： TerraPower, LLC
摘要： A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.
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公开(公告)号：US10522259B2
公开(公告)日：2019-12-31
申请号：US15329646
申请日：2016-01-25
申请人： CLEAR INC.
发明人： Osao Sumita , Isao Ueno , Takehiko Yokomine
IPC分类号： G21C7/10 , G21D3/12 , G21C1/02 , G21C7/02 , G21C7/28 , G21C1/06 , G21C11/06 , G21D3/16 , G21C7/00 , G21D3/08
摘要： A nuclear power generation system being safe and easily controlled by load following. The nuclear power generation system has a nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core having metallic fuel containing at least one selected from uranium-235, uranium-238 and plutonium-239; a reactor vessel containing the reactor core; metallic sodium loaded into the reactor vessel and heated by the reactor core; and a neutron reflector for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the reactor core being maintained at or above about 1. The neutron reflector is coupled to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector.
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公开(公告)号：US09799417B2
公开(公告)日：2017-10-24
申请号：US12462203
申请日：2009-07-30
申请人： Roderick A. Hyde , Muriel Y. Ishikawa , Nathan P. Myhrvold , Joshua C. Walter , Thomas Allan Weaver , Lowell L. Wood, Jr. , Victoria Y. H. Wood
发明人： Roderick A. Hyde , Muriel Y. Ishikawa , Nathan P. Myhrvold , Joshua C. Walter , Thomas Allan Weaver , Lowell L. Wood, Jr. , Victoria Y. H. Wood
摘要： A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system.
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公开(公告)号：US09754689B2
公开(公告)日：2017-09-05
申请号：US14386156
申请日：2013-03-25
发明人： Yutaka Ueyama , Wataru Sugino
IPC分类号： G21C17/022 , G21D3/08 , C02F101/00 , C02F103/02
CPC分类号： G21C17/0225 , C02F2101/006 , C02F2103/023 , C02F2305/04 , G21D3/08 , Y02E30/40
摘要： A radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced are provided. The radiation source reducing system for nuclear power plants includes a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system. The dispersant is polyacrylic acid, and has an average molecular weight in a range of 16000 to 26000, inclusive.
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公开(公告)号：US09410252B2
公开(公告)日：2016-08-09
申请号：US14345148
申请日：2012-09-13
申请人： Masato Okamura , Tetsuo Oosato , Kazuo Murakami , Seiji Yamamoto , Hiroyuki Arai , Hidehiro Urata , Hajime Hirasawa , Osamu Shibasaki , Koji Negishi
发明人： Masato Okamura , Tetsuo Oosato , Kazuo Murakami , Seiji Yamamoto , Hiroyuki Arai , Hidehiro Urata , Hajime Hirasawa , Osamu Shibasaki , Koji Negishi
IPC分类号： C23F11/18 , C23F11/08 , G21C17/022 , G21D3/08 , C23F15/00
CPC分类号： C23F11/08 , C23F11/18 , C23F11/185 , C23F15/00 , G21C17/0225 , G21D3/08 , Y02E30/40
摘要： A method for injecting a corrosion inhibitor injecting an oxidant and an anticorrosive agent-pH adjusting agent complex including an anticorrosive agent and a pH adjusting agent adsorbed on a surface of the anticorrosive agent into high temperature water in contact with a surface of a metal structural material and irradiating the high temperature water with a radioactive ray or an ultraviolet ray, wherein the anticorrosive agent of the anticorrosive agent-pH adjusting agent complex has, on the surface of the anticorrosive agent, an active site where the pH adjusting agent reacts with the oxidant, and the pH adjusting agent present on the surface of the anticorrosive agent of the anticorrosive agent-pH adjusting agent complex and/or in the high temperature water is oxidized with the oxidant by the irradiation with the radioactive ray or the ultraviolet ray to change pH adjusting ability of the pH adjusting agent and shift a pH of the high temperature water to a neutral side, and thereby deposition of the anticorrosive agent 11 to the metal structural material 65 is accelerated.
摘要翻译： 一种将注入氧化剂的腐蚀抑制剂和防腐蚀剂 - pH调节剂复合物的方法，所述防腐蚀剂 - pH调节剂复合物包括吸附在防腐剂表面上的耐腐蚀剂和pH调节剂，所述抗腐蚀剂和pH调节剂与金属结构材料表面接触的高温水中 并用放射线或紫外线照射高温水，其中防腐剂 - pH调节剂复合物的防腐剂在防腐剂的表面上具有pH调节剂与氧化剂反应的活性位点 ，并且在抗腐蚀剂 - pH调节剂配合物的防腐剂的表面上和/或在高温水中存在的pH调节剂用氧化剂通过用放射线或紫外线照射而被氧化以改变pH 调节pH调节剂的能力并将高温水的pH值转移到中性侧，从而进行 加速了防锈剂11向金属结构材料65的沉积。
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7.发明授权Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria 有权用于设计满足许可标准的核反应堆核心的计算机实现方法和系统公开(公告)号：US08873698B2
公开(公告)日：2014-10-28
申请号：US11642871
申请日：2006-12-21
IPC分类号： G06F17/50 , G06G7/54 , G21D3/00 , G21C19/20 , G21C17/00 , G21D3/04 , G21D3/08 , G06F17/00 , G06G7/00
CPC分类号： G21C17/00 , G21C19/205 , G21D3/001 , G21D3/04 , G21D3/08 , G21D2003/002 , G21Y2002/201 , G21Y2002/202 , G21Y2002/203 , G21Y2002/304 , G21Y2004/40 , G21Y2004/403 , Y02E30/39
摘要： In a computer-implemented method of designing a nuclear reactor of a given reactor plant, an initial, test reactor core design is generated for the given plant based on a plurality of limits input by a user. The limits include a plurality of transient licensing constraints to be satisfied for operating the given plant. The method includes selecting, from a set of automated tools, one or more automated tools to evaluate the test core design, and operating one of more of selected automated tools to output data for display to the user. The displayed data is related to a core design that satisfies the limits inclusive of the transient licensing constraints.
摘要翻译： 在设计给定反应堆设备的核反应堆的计算机实现的方法中，基于由用户输入的多个限制，为给定设备产生初始的测试反应堆核心设计。 这些限制包括要为运行给定设备而满足的许多暂时许可限制。 该方法包括从一组自动化工具中选择一个或多个自动化工具来评估测试核心设计，以及操作多个所选择的自动化工具之一来输出用于显示给用户的数据。 显示的数据与满足临时许可限制的限制的核心设计相关。
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8.发明申请Method for recognizing step movement sequence of control rod drive mechanism of nuclear reactor 有权识别核反应堆控制棒驱动机构的步进运动顺序的方法公开(公告)号：US20050286673A1
公开(公告)日：2005-12-29
申请号：US10874235
申请日：2004-06-24
申请人： Choon-Kyung Kim , Seog-Joo Kim , Jong-Min Cheon , Jong-Moo Lee , Kook-Hun Kim , Soon-Man Kwon
发明人： Choon-Kyung Kim , Seog-Joo Kim , Jong-Min Cheon , Jong-Moo Lee , Kook-Hun Kim , Soon-Man Kwon
摘要： A method for recognizing the step movement sequence of a control rod drive mechanism of a nuclear reactor, which withdraws and inserts a control rod of a nuclear reactor, includes the steps of: measuring current and voltage flowing through an electromagnetic coil used in the control rod drive mechanism of the nuclear reactor; calculating inductance of the coil by using the measured current and voltage; calculating a distance between a rotor and a stator of the control rod drive mechanism on the basis of the calculated inductance; and recognizing the step movement sequence of the control rod drive mechanism on the basis of the calculated distance. This method ensures good reliability in determining the step movement sequence, allows easy implementation using a digital signal processor, and is hardly affected by external factors such as noise.
摘要翻译： 用于识别放出并插入核反应堆的控制棒的核反应堆的控制棒驱动机构的步进运动顺序的方法包括以下步骤：测量流过控制棒中使用的电磁线圈的电流和电压 核反应堆的驱动机制; 使用测量的电流和电压计算线圈的电感; 基于计算的电感计算控制棒驱动机构的转子和定子之间的距离; 并基于计算出的距离识别控制棒驱动机构的步进运动顺序。 该方法确保了确定步进运动顺序的良好可靠性，允许使用数字信号处理器轻松实现，并且几乎不受外部因素如噪声的影响。
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公开(公告)号：US06938584B2
公开(公告)日：2005-09-06
申请号：US10885681
申请日：2004-07-08
申请人： Suk Whun Sohn , In Ho Song , Jong Joo Sohn , Jong Tae Seo
发明人： Suk Whun Sohn , In Ho Song , Jong Joo Sohn , Jong Tae Seo
CPC分类号： G21D3/14 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a flow error signal corresponding to a difference between a steam flow signal and a feedwater flow signal; and a water level correction error signal generator for generating a water level correction error signal corresponding to a sum of a water level measurement signal and the flow error signal. A second detection unit includes: a pressure drop sensor unit for detecting a pressure difference between front and rear portions of at least one feedwater control valve among the main feedwater control valves and the downcorner feedwater control valves and generating a pressure drop signal corresponding to the detected pressure difference; a pressure drop setup value signal generator for generating a pressure drop setup value signal corresponding to a previously set pressure drop setup value of the feedwater control valves; and a pressure drop error signal generator for comparing the pressure drop signal with the pressure drop setup value signal and generating a pressure drop error signal. A control unit controls the main feedwater pump based on a correction control signal output from the correction control signal generator.
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10.发明授权Co-deposition of palladium during oxide film growth in high-temperature water to mitigate stress corrosion cracking 失效在高温水中氧化膜生长期间钯的共沉积以减轻应力腐蚀开裂
公开(公告)号：US5768330A
公开(公告)日：1998-06-16
申请号：US729024
申请日：1996-10-10
IPC分类号： G21D1/00 , B01J37/03 , C23C8/80 , C23C12/00 , C23F11/08 , C23F11/18 , G01N17/02 , G21C17/02 , G21C17/022 , G21C19/28 , G21C19/30 , G21C19/307 , G21D3/08 , G21C9/00
CPC分类号： G21C17/0225 , B01J37/031 , C23C12/00 , C23C8/80 , C23F11/08 , C23F11/18 , G01N17/02 , G21C17/02 , G21C19/28 , G21C19/30 , G21C19/307 , G21C17/022 , G21Y2002/102 , G21Y2002/103 , G21Y2002/104 , G21Y2002/201 , G21Y2002/204 , G21Y2004/10 , G21Y2004/101 , G21Y2004/20 , G21Y2004/30 , G21Y2004/302 , G21Y2004/40
摘要： A method for improving the performance and longevity of coatings of metal deposited from aqueous solutions of inorganic, organic or oraganometallic metal compounds. The method involves co-deposition of noble metal or corrosion-inhibiting non-noble metal during growth of oxide film on a component made of alloy, e.g., stainless steels and nickel-based alloys. The result is a metal-doped oxide film having a relatively longer life in the reactor operating environment. In particular, incorporation of palladium into the film provides greatly increased catalytic life as compared to palladium coatings which lie on the oxide surface.
摘要翻译： 一种改善由无机，有机或金属金属化合物的水溶液沉积的金属涂层的性能和寿命的方法。 该方法包括在由诸如不锈钢和镍基合金的合金制成的部件上氧化膜生长期间共沉积贵金属或腐蚀抑制非贵金属。 结果是在反应器操作环境中具有相对较长寿命的金属掺杂氧化物膜。 特别地，与位于氧化物表面上的钯涂层相比，将钯引入膜中提供了大大增加的催化寿命。
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