公开(公告)号：US20120106693A1

公开(公告)日：2012-05-03

申请号：US13280585

申请日：2011-10-25

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

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

IPC分类号： G21C1/02 ,  C22C38/44 ,  G21C1/00 ,  C22C38/48 ,  C22C38/54 ,  C22C38/02 ,  C21D8/00 ,  C22C38/46

CPC分类号： C22C38/001 ,  C21D6/002 ,  C21D2211/005 ,  C21D2211/008 ,  C22C1/02 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

摘要： Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with to superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

摘要翻译： 本文公开了一种高Cr铁素体/马氏体钢，其包含0.04至0.13重量％的碳，0.03至0.07重量％的硅，0.40至0.50重量％的锰，0.40至0.50重量％的镍，8.5至9.5 铬，0.45〜0.55重量％的钼，0.10〜0.25重量％的钒，0.02〜0.10重量％的钽，0.21〜0.25重量％的铌，1.5〜3.0重量％的钨 ，0.015〜0.025重量％的氮，0.01〜0.02重量％的硼和铁的平衡。 通过调节氮，合金元素含量，提供高Cr铁素体/马氏体钢，具有优异的抗拉强度和抗蠕变性，可以有效地用作钠冷快堆的核心成分材料（ SFR）。

公开(公告)号：US20110162764A1

公开(公告)日：2011-07-07

申请号：US12984811

申请日：2011-01-05

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

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

IPC分类号： C21D8/02 ,  C21D6/00 ,  C22C38/00 ,  C22C38/54 ,  C22C38/46 ,  C22C38/44 ,  C22C38/48

CPC分类号： C21D6/002 ,  C21D1/28 ,  C21D7/13 ,  C21D8/0221 ,  C21D2211/005 ,  C21D2211/008 ,  C22C1/02 ,  C22C38/001 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54

摘要： High-Cr ferritic/martensitic steels having an improved tensile strength and creep resistance are provided, which includes 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron, and optionally, 0.002˜0.010 weight % of phosphorus or 0.01˜0.08 weight % of zirconium, and iron balance. By regulating the contents of alloying elements such as niobium, tantalum, tungsten, nitrogen, boron, zirconium, carbon, the high-Cr ferritic/martensitic steels with superior tensile strength and creep resistance are provided, and can be effectively used as an in-core structural material for Generation IV sodium-cooled fast reactor (SFR) which is used under high temperature and high irradiation conditions.

摘要翻译： 提供了具有改进的抗拉强度和抗蠕变性的高Cr铁素体/马氏体钢，其包括0.04〜0.13重量％的碳，0.03〜0.07重量％的硅，0.40〜0.50重量％的锰，0.40〜0.50重量％的 镍，8.5〜9.5重量％的铬，0.45〜0.55重量％的钼，0.10〜0.25重量％的钒，0.02〜0.10重量％的钽，0.15〜0.25重量％的铌，1.5〜3.0重量％的钨， 0.05〜0.12重量％的氮，0.004〜0.008重量％的硼，以及任选的0.002〜0.10重量％的磷或0.01〜0.08重量％的锆和铁的平衡。 通过调节铌，钽，钨，氮，硼，锆，碳等合金元素的含量，提供了具有优异的抗拉强度和抗蠕变性的高Cr铁素体/马氏体钢， 在高温高照射条件下使用的第IV代钠冷快堆（SFR）的核心结构材料。

公开(公告)号：US09598750B2

公开(公告)日：2017-03-21

申请号：US13280585

申请日：2011-10-25

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

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

IPC分类号： C22C38/02 ,  C22C38/00 ,  C21D6/00 ,  C22C1/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

CPC分类号： C22C38/001 ,  C21D6/002 ,  C21D2211/005 ,  C21D2211/008 ,  C22C1/02 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

摘要： Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

公开(公告)号：US08155260B2

公开(公告)日：2012-04-10

申请号：US12110775

申请日：2008-04-28

申请人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

发明人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

IPC分类号： G21C3/00

CPC分类号： G21C3/20 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/40

摘要： Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

摘要翻译： 本文公开了一种用于快堆的核燃料棒及其制造方法，其包括形成在包层的内表面上的氧化物被覆层。 用于快堆的核燃料棒（包括形成在包层内表面上的氧化物涂层）可以增加快堆的金属燃料块的最大允许燃耗和最大允许温度，从而延长其在 快堆，从而提高经济效益。 此外，与现有的形成金属衬垫的方法相比，燃料棒的制造更简单，并且所公开的方法能够以简单和成本有效的方式制造燃料棒的包层。

公开(公告)号：US20090141851A1

公开(公告)日：2009-06-04

申请号：US12110775

申请日：2008-04-28

申请人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

发明人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

IPC分类号： G21C3/07

CPC分类号： G21C3/20 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/40

摘要： Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

摘要翻译： 本文公开了一种用于快堆的核燃料棒及其制造方法，其包括形成在包层的内表面上的氧化物被覆层。 用于快堆的核燃料棒（包括形成在包层内表面上的氧化物涂层）可以增加快堆的金属燃料块的最大允许燃耗和最大允许温度，从而延长其在 快堆，从而提高经济效益。 此外，与现有的形成金属衬垫的方法相比，燃料棒的制造更简单，并且所公开的方法能够以简单和成本有效的方式制造燃料棒的包层。

公开(公告)号：US20050135544A1

公开(公告)日：2005-06-23

申请号：US10677941

申请日：2003-10-01

申请人： Jae-Hyuk Eoh ,  Yoon-Sub Sim ,  Seong-O Kim ,  Dohee Hahn

发明人： Jae-Hyuk Eoh ,  Yoon-Sub Sim ,  Seong-O Kim ,  Dohee Hahn

IPC分类号： G21C1/02 ,  G21C9/00 ,  G21C15/18

CPC分类号： G21C1/03 ,  G21C15/18 ,  G21Y2002/207 ,  G21Y2002/304 ,  G21Y2002/50 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/34 ,  Y02E30/35

摘要： Dis0closed herein is a direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool. In the circular vertical tube is disposed a sodium-sodium heat exchanger, which is connected to a sodium-air heat exchanger mounted above a reactor building via a heat removing sodium loop, in such a manner that it is placed at the position higher than a liquid level of the sodium in the cold pool under the normal steady-state conditions. Under transient conditions, for example, when the normal heat removal system breaks down, the primary pump is automatically tripped, and accordingly the liquid level of the cold pool rises with the result that the liquid level difference between the hot pool and the cold pool is eliminated. Consequently, the sodium-sodium heat exchanger makes direct contact with the hot sodium so that core decay heat is discharged into a final heat sink, for example, the atmosphere. In this way, the decay heat removal system of the present invention is operated on the basis of a completely passive concept with improved operational reliability. Heat loss incurred by the decay heat removal system is minimized under normal steady-state conditions, whereby economical efficiency is maximized. The decay heat removal system of the present invention can effectively remove core decay heat under transient conditions. Moreover, the decay heat removal system of the present invention provides an additional heat removal capacity obtained by the passive vessel cooling system, whereby the decay heat removal system of the present invention can be easily applied to a large thermal rated liquid metal reactor.

公开(公告)号：US07522693B2

公开(公告)日：2009-04-21

申请号：US10677941

申请日：2003-10-01

申请人： Jae-Hyuk Eoh ,  Yoon-Sub Sim ,  Seong-O Kim ,  Dohee Hahn

发明人： Jae-Hyuk Eoh ,  Yoon-Sub Sim ,  Seong-O Kim ,  Dohee Hahn

IPC分类号： G21C9/00

CPC分类号： G21C1/03 ,  G21C15/18 ,  G21Y2002/207 ,  G21Y2002/304 ,  G21Y2002/50 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/34 ,  Y02E30/35

摘要： A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool. In the circular vertical tube is disposed a sodium-sodium heat exchanger, which is connected to a sodium-air heat exchanger mounted above a reactor building via a heat removing sodium loop, in such a manner that it is placed at the position higher than a liquid level of the sodium in the cold pool under the normal steady-state conditions.

摘要翻译： 一种直接游泳池冷却型被动安全等级衰变除热方法和系统，用于在普通散热系统发生故障时，在池式液态金属反应器中去除核心衰变热。 在包括反应器容器的液态金属反应器中，其内部被分配在核心上方的热池和围绕核心的冷库，使得热池和冷库之间的液位差由主泵头保持 在正常稳态条件下，以这样的方式设置至少一个圆形垂直管，使得圆形垂直管中的钠保持与冷库中钠的液面相同的液面。 在圆形垂直管中设置钠钠热交换器，该钠钠热交换器通过除热钠环连接到安装在反应堆建筑物上方的钠空气热交换器，使得它被放置在高于 液态钠在冷库中处于正常稳态条件下。