公开(公告)号：US08444782B2

公开(公告)日：2013-05-21

申请号：US12612101

申请日：2009-11-04

申请人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

发明人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

IPC分类号： C21D8/00

CPC分类号： C21D8/1266 ,  C21D2211/004 ,  C21D2211/005 ,  C21D2211/008

摘要： Provided is a method of manufacturing a high strength ferritic/martensitic steel. The method includes melting a ferritic/martensitic steel, hot-working the melted ferritic/martensitic steel, normalizing the hot-worked ferritic/martensitic steel at a temperature of about 1050° C. to about 1200° C., tempering the ferritic/martensitic steel at a temperature of about 600° C. or less, and leaving MX precipitates while preventing a M23C6 precipitate from being precipitated, and cold-working and thermal-treating the ferritic/martensitic steel in a multistage fashion, and precipitating M23C6 precipitates. Through the above described configuration, the high strength ferritic/martensitic steel that prevents a ductility from being deteriorated even in a high-temperature environment may be manufactured.

摘要翻译： 提供一种制造高强度铁素体/马氏体钢的方法。 该方法包括熔化铁素体/马氏体钢，对熔融的铁素体/马氏体钢进行热加工，使热处理的铁素体/马氏体钢在约1050℃至约1200℃的温度下归一化，回火铁素体/马氏体 钢在约600℃以下，留下MX析出物，同时防止M23C6沉淀物析出，并对铁素体/马氏体钢进行多级冷加工和热处理，并析出M23C6沉淀物。 通过上述结构，可以制造即使在高温环境下也能够防止延展性劣化的高强度铁素体/马氏体钢。

公开(公告)号：US20100108207A1

公开(公告)日：2010-05-06

申请号：US12612101

申请日：2009-11-04

申请人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

发明人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

IPC分类号： C21D8/00

CPC分类号： C21D8/1266 ,  C21D2211/004 ,  C21D2211/005 ,  C21D2211/008

摘要： Provided is a method of manufacturing a high strength ferritic/martensitic steel. The method includes melting a ferritic/martensitic steel, hot-working the melted ferritic/martensitic steel, normalizing the hot-worked ferritic/martensitic steel at a temperature of about 1050° C. to about 1200° C., tempering the ferritic/martensitic steel at a temperature of about 600° C. or less, and leaving MX precipitates while preventing a M23C6 precipitate from being precipitated, and cold-working and thermal-treating the ferritic/martensitic steel in a multistage fashion, and precipitating M23C6 precipitates. Through the above described configuration, the high strength ferritic/martensitic steel that prevents a ductility from being deteriorated even in a high-temperature environment may be manufactured.

摘要翻译： 提供一种制造高强度铁素体/马氏体钢的方法。 该方法包括熔化铁素体/马氏体钢，对熔融的铁素体/马氏体钢进行热加工，使热处理的铁素体/马氏体钢在约1050℃至约1200℃的温度下归一化，回火铁素体/马氏体 钢在约600℃以下，留下MX析出物，同时防止M23C6沉淀物析出，并对铁素体/马氏体钢进行多级冷加工和热处理，并析出M23C6沉淀物。 通过上述结构，可以制造即使在高温环境下也能够防止延展性劣化的高强度铁素体/马氏体钢。

公开(公告)号：US20100135452A1

公开(公告)日：2010-06-03

申请号：US12443519

申请日：2007-10-16

申请人： Ser Gi Hong ,  Yeong-II Kim ,  Sang Ji Kim ,  Do-Hee Hahn

发明人： Ser Gi Hong ,  Yeong-II Kim ,  Sang Ji Kim ,  Do-Hee Hahn

IPC分类号： G21C3/06 ,  G21C1/02

CPC分类号： G21C1/022 ,  G21C3/04 ,  G21C5/02 ,  G21C7/005 ,  G21Y2002/304 ,  G21Y2004/30 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/39

摘要： A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly (1) of a liquid-metal cooled fast reactor includes nuclear fuel assemblies (1a, 1b and 1c) in inner, middle and outer reactor core regions, respectively, and is installed in a hexagonal duct (3) with nuclear fuel materials (2-2a, 2-2b and 2-2c) surrounded by respective claddings (2-1a, 2-1b and 2-1c), and the claddings (2-1a, 2-1b and 2-1c) of a nuclear fuel rod (2a) in the inner reactor core region, a nuclear fuel rod (2b) in the middle reactor core region and a nuclear fuel rod (2c) in the outer reactor core region are formed at different thicknesses. The reactor core can flatten power distribution using a single-enrichment nuclear fuel in the liquid-metal cooled fast reactor.

摘要翻译： 一种液态金属冷却的快堆堆芯，其具有核反应堆核心区域中具有不同包层厚度的核燃料棒组成的核燃料组件，其中：液态金属冷却快堆的核燃料组件（1）包括核燃料组件 1a，1b和1c）分别安装在内，中，外反应堆堆芯区域内，并安装在由相应包层围绕的核燃料材料（2-2a，2-2b和2-2c）的六边形管道（3） 2-1a，2-1b和2-1c）和内反应堆芯区域中的核燃料棒（2a）的包层（2-1a，2-1b和2-1c），核燃料棒（2b） ）和外反应堆芯区域中的核燃料棒（2c）形成为不同的厚度。 反应堆堆芯可以在液态金属冷却的快速反应堆中使用单浓度核燃料来平坦化配电。

公开(公告)号：US07774149B2

公开(公告)日：2010-08-10

申请号：US12051328

申请日：2008-03-19

申请人： Tae-Joon Kim ,  Ji-Young Jeong ,  Do-Hee Hahn

发明人： Tae-Joon Kim ,  Ji-Young Jeong ,  Do-Hee Hahn

IPC分类号： G01G23/00

CPC分类号： G01M3/24 ,  F22B37/003 ,  F22B37/421 ,  G21C17/00 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/50 ,  G21Y2004/40

摘要： A water leakage-acoustic sensing method in a steam generator of a sodium-cooled fast reactor, the method including: calculating a standard deviation and an average of an octave band by octave band analysis of an input signal sound received from at least one predetermined acoustic sensor; comparing the calculated standard deviation and the calculated average of the octave band, and determining a size of the octave band based on a comparison result; calculating an average of standard deviations of the octave band recomposed by the determined size and normalizing the average of standard deviations; applying a predetermined weight, established by a predetermined neural network learning algorithm, to the normalized average of standard deviations; and generating leakage determination data based on the average of standard deviations to which the weight is applied.

摘要翻译： 一种钠冷快堆的蒸汽发生器中的漏水声检测方法，该方法包括：通过从至少一个预定声学接收的输入信号声音的八度频带分析来计算八度波段的标准偏差和平均值 传感器; 比较计算的标准偏差和计算的倍频程频带的平均值，并且基于比较结果确定倍频程带的大小; 计算由确定的尺寸重组的倍频程带的标准偏差的平均值，并标准化标准偏差的平均值; 将由预定神经网络学习算法建立的预定权重应用于标准偏差的归一化平均值; 以及基于施加所述权重的标准偏差的平均值来生成泄漏确定数据。

公开(公告)号：US20080234950A1

公开(公告)日：2008-09-25

申请号：US12051328

申请日：2008-03-19

申请人： Tae-Joon KIM ,  Ji-Young Jeong ,  Do-Hee Hahn

发明人： Tae-Joon KIM ,  Ji-Young Jeong ,  Do-Hee Hahn

IPC分类号： G01F23/296

CPC分类号： G01M3/24 ,  F22B37/003 ,  F22B37/421 ,  G21C17/00 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/50 ,  G21Y2004/40

摘要： A water leakage-acoustic sensing method in a steam generator of a sodium-cooled fast reactor, the method including: calculating a standard deviation and an average of an octave band by octave band analysis of an input signal sound received from at least one predetermined acoustic sensor; comparing the calculated standard deviation and the calculated average of the octave band, and determining a size of the octave band based on a comparison result; calculating an average of standard deviations of the octave band recomposed by the determined size and normalizing the average of standard deviations; applying a predetermined weight, established by a predetermined neural network learning algorithm, to the normalized average of standard deviations; and generating leakage determination data based on the average of standard deviations to which the weight is applied.

摘要翻译： 一种钠冷快堆的蒸汽发生器中的漏水声检测方法，该方法包括：通过从至少一个预定声学接收的输入信号声音的八度频带分析来计算八度波段的标准偏差和平均值 传感器; 比较计算的标准偏差和计算的倍频程频带的平均值，并且基于比较结果确定倍频程带的大小; 计算由确定的尺寸重组的倍频程带的标准偏差的平均值，并标准化标准偏差的平均值; 将由预定神经网络学习算法建立的预定权重应用于标准偏差的归一化平均值; 以及基于施加所述权重的标准偏差的平均值来生成泄漏确定数据。

公开(公告)号：US08693611B2

公开(公告)日：2014-04-08

申请号：US12443519

申请日：2007-10-16

申请人： Ser Gi Hong ,  Yeong-Il Kim ,  Sang Ji Kim ,  Do-Hee Hahn

发明人： Ser Gi Hong ,  Yeong-Il Kim ,  Sang Ji Kim ,  Do-Hee Hahn

IPC分类号： G21C3/32

CPC分类号： G21C1/022 ,  G21C3/04 ,  G21C5/02 ,  G21C7/005 ,  G21Y2002/304 ,  G21Y2004/30 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/39

摘要： A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly (1) of a liquid-metal cooled fast reactor includes nuclear fuel assemblies (1a, 1b and 1c) in inner, middle and outer reactor core regions, respectively, and is installed in a hexagonal duct (3) with nuclear fuel materials (2-2a, 2-2b and 2-2c) surrounded by respective claddings (2-1a, 2-1b and 2-1c), and the claddings (2-1a, 2-1b and 2-1c) of a nuclear fuel rod (2a) in the inner reactor core region, a nuclear fuel rod (2b) in the middle reactor core region and a nuclear fuel rod (2c) in the outer reactor core region are formed at different thicknesses. The reactor core can flatten power distribution using a single-enrichment nuclear fuel in the liquid-metal cooled fast reactor.

摘要翻译： 一种液态金属冷却的快堆堆芯，其具有核反应堆核心区域中具有不同包层厚度的核燃料棒组成的核燃料组件，其中：液态金属冷却快堆的核燃料组件（1）包括核燃料组件 1a，1b和1c）分别安装在内，中，外反应堆堆芯区域内，并安装在由相应包层围绕的核燃料材料（2-2a，2-2b和2-2c）的六边形管道（3） 2-1a，2-1b和2-1c）和内反应堆芯区域中的核燃料棒（2a）的包层（2-1a，2-1b和2-1c），核燃料棒（2b） ）和外反应堆芯区域中的核燃料棒（2c）形成为不同的厚度。 反应堆堆芯可以在液态金属冷却的快速反应堆中使用单浓度核燃料来平坦化配电。