专利快速检索-快速检索全球专利，免费商用专利数据库-IPRDB

71. 发明授权

KR101378066B1 합금원소의 첨가량을 낮추어 부식저항성을 향상시킨 핵연료 피복관용 지르코늄 합금 조성물 및 이를 이용한 지르코늄 합금 핵연료 피복관의 제조방법 有权
标题翻译：用于核燃料包覆的锆合金，通过减少合金元素的量具有优异的耐腐蚀性，以及使用其的锆合金核燃料包层的制备方法
公开(公告)号：KR101378066B1
公开(公告)日：2014-03-28
申请号：KR1020120020272
申请日：2012-02-28
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 박정용 , 최병권 , 김현길 , 박상윤 , 정양일 , 박동준 , 구양현
IPC分类号： C22C16/00 , G21C3/06
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21C21/10 , Y02E30/40
摘要： 본 발명은 합금원소의 첨가량을 낮추어 부식저항성을 향상시킨 핵연료 피복관용 지르코늄 합금 조성물 및 이를 이용한 지르코늄 합금 핵연료 피복관의 제조방법에 관한 것으로, 상세하게는 니오븀(Nb) 0.2 ~ 0.5 중량%; 철(Fe) 0.2 ~ 0.6 중량%; 크롬(Cr) 0.3 ~ 0.5 중량%; 산소(O) 0.1 ~ 0.15 중량%; 규소(Si) 0.008 ~ 0.012 중량% 및 지르코늄(Zr) 잔부로 이루어지고, 상기 니오븀, 철 및 크롬의 총 함량이 1.1 ~ 1.2 중량%인 것을 특징으로 하는 핵연료 피복관용 지르코늄 합금 조성물을 제공한다. 본 발명에 따른 핵연료 피복관용 지르코늄 합금 조성물을 이용하여 핵연료 피복관을 제조함으로써, 원자로의 정상가동 조건뿐만 아니라 사고조건하에서도 핵연료 피복관의 우수한 내산화성을 확보할 수 있어 핵연료의 경제성 및 안전성을 동시에 향상시킬 수 있다.

72. 发明公开

KR1020130098618A 사고조건 하의 원자로 내에서 우수한 내산화성을 나타내는 핵연료 피복관용 지르코늄 합금 조성물, 이를 이용하여 제조한 지르코늄 합금 핵연료 피복관 및 이의 제조방법 无效
标题翻译：在反应堆事故条件下具有超级氧化电阻的核燃料层的ZIRCONIUM合金，使用其制备的ZIRCONIUM合金核燃料层及其制备方法
公开(公告)号：KR1020130098618A
公开(公告)日：2013-09-05
申请号：KR1020120020271
申请日：2012-02-28
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 박정용 , 김현길 , 최병권 , 박상윤 , 정양일 , 박동준 , 구양현
IPC分类号： C22C16/00 , G21C3/07
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21C21/10 , Y02E30/40
摘要： PURPOSE: Zirconium alloys for nuclear fuel claddings and zirconium alloy nuclear fuel claddings manufactured by using thereof and a method of manufacturing thereof are provided to secure an excellent oxidation resistance of a nuclear fuel cladding not only under an accident condition but also in a normal operation condition of a nuclear reactor. CONSTITUTION: Zirconium alloys for nuclear fuel claddings comprise 1.0-1.2 weight% of niobium (Nb), elements which is more than one kind selected from a group consisting of tin (Sn), iron (Fe), and chrome (Cr), 0.02-0.1 weight% of copper (Cu), 0.1-0.15 weight% of oxygen (O), 0.008-0.012 weight% of silicon (Si), and remainders of zirconium (Zr). A composition selected among 0.1-0.3 weight% of tin (Sn), and 0.3-0.8 weight% of iron (Fe), and 0.1-0.3 weight% of chrome (Cr) is included. The Zirconium alloys comprise 1.1 weight% of niobium (Nb), two kinds of elements selected from a group consisting of tin (Sn), iron (Fe), and chrome (Cr), 0.05 weight% of copper (Cu), 0.12 weight% of oxygen (O), 0.01 weight% of silicon (Si), and remainders of zirconium (Zr). A composition selected among 0.2 weight% of tin (Sn), and 0.5 weight% of iron (Fe), and 0.1-0.2 weight% of chrome (Cr) is included. [Reference numerals] (AA) Amount of weight increase (mg/dm^2); (BB) 1200 °C 1800 seconds; (CC) Example 1; (DD) Example 4; (EE) Example 6; (FF) Comparative example 2
摘要翻译：目的：提供用于核燃料包层的锆合金和使用其制造的锆合金核燃料包层及其制造方法，以确保不仅在事故条件下而且在正常操作条件下核燃料包覆的优异的抗氧化性的核反应堆。构成：用于核燃料包层的锆合金包含铌（Nb）的1.0-1.2重量％，选自由锡（Sn），铁（Fe）和铬（Cr）组成的组中的一种以上的元素，0.02 -0.1重量％的铜（Cu），0.1-0.15重量％的氧（O），0.008-0.012重量％的硅（Si）和余量的锆（Zr）。包括选自0.1-0.3重量％的锡（Sn）和0.3-0.8重量％的铁（Fe）和0.1-0.3重量％的铬（Cr）的组合物。锆合金包括1.1重量％的铌（Nb），选自锡（Sn），铁（Fe）和铬（Cr），0.05重量％的铜（Cu），0.12重量的两种元素氧（O）％，硅（Si）0.01重量％，锆（Zr）余量。包括选自锡（Sn）0.2重量％和铁（Fe）0.5重量％和铬（Cr）0.1-0.2重量％的组合物。（AA）重量增加量（mg / dm ^ 2）; （BB）1200℃1800秒; （CC）实施例1; （DD）实施例4 （EE）实施例6; （FF）比较例2

73. 发明授权

KR101225005B1 핵연료 소결체-피복관 상호작용 측정 맨드렐 셀 및 이를 구비한 시스템 有权
标题翻译：颗粒包覆相互作用测试心轴细胞及其组成的系统
公开(公告)号：KR101225005B1
公开(公告)日：2013-01-22
申请号：KR1020110042125
申请日：2011-05-03
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 박상윤 , 박정용 , 최병권 , 김현길 , 정양일 , 박동준
IPC分类号： G21C17/06 , G21D3/04
CPC分类号： Y02E30/40
摘要： 핵연료 봉의 소결체-피복관 상호작용 측정 맨드렐 셀 및 이를 구비하는 시스템을 개시한다. 상기 핵연료 봉의 소결체-피복관 상호작용 측정 시스템은 요오드 분위기에서 피복관 시편을 인장기를 통해 국부적으로 팽창시켜 상기 피복관 시편에 응력부식균열이 일어나도록 하여 상기 피복관 시편의 변형량을 조절하는 맨드렐 셀본체, 상기 맨드렐 셀본체 내의 요오드를 공급하며, 상기 요오드의 농도를 조절하는 요오드 공급부, 상기 맨드렐 셀본체 내에 공급된 요오드의 분압을 조절하는 분압조절부 및 상기 피복관 시편의 변형된 데이터를 실시간으로 저장하는 데이터 저장부를 포함한다.
摘要翻译：目的：提供一种相互作用测量芯轴单元及包含该相互作用测量芯轴单元的系统，以便使用针式心轴精细控制提供给薄核燃料包层的变形量。构成：芯棒电池体（200）通过在碘分离器中局部地延伸包覆管样品，在包壳试样中产生SCC（应力腐蚀开裂）。心轴芯体控制包壳试样的变形量。碘提供单元（300）通过向心轴细胞体提供碘来控制碘的浓度。分压控制单元（400）控制提供给心轴芯体的碘的压力。数据存储单元（500）实时存储转换后的数据。

74. 发明公开

KR1020120124301A 핵연료 소결체-피복관 상호작용 측정 맨드렐 셀 및 이를 구비한 시스템 有权
标题翻译：颗粒包覆相互作用测试心轴细胞及其组成的系统
公开(公告)号：KR1020120124301A
公开(公告)日：2012-11-13
申请号：KR1020110042125
申请日：2011-05-03
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 박상윤 , 박정용 , 최병권 , 김현길 , 정양일 , 박동준
IPC分类号： G21C17/06 , G21D3/04
CPC分类号： Y02E30/40 , G21C17/06 , G21C3/06
摘要： PURPOSE: An interaction measurement mandrel cell and system including the same are provided to minutely control deformation amount provided to a thin nuclear fuel cladding using a pin type mandrel. CONSTITUTION: A mandrel cell body(200) generates SCC(Stress Corrosion Cracking) in a cladding tube sample by locally extending the cladding tube sample in an iodine separator. The mandrel cell body controls the deformation amount of the cladding tube sample. The iodine providing unit(300) controls the concentration of the iodine by providing the iodine to the mandrel cell body. A partial pressure control unit(400) controls the pressure of the iodine provided to the mandrel cell body. A data storage unit(500) stores the converted data in real time.
摘要翻译：目的：提供一种相互作用测量芯轴单元及包含该相互作用测量芯轴单元的系统，以便使用针式心轴精细控制提供给薄核燃料包层的变形量。构成：芯棒电池体（200）通过在碘分离器中局部地延伸包覆管样品，在包壳试样中产生SCC（应力腐蚀开裂）。心轴芯体控制包壳试样的变形量。碘提供单元（300）通过向心轴细胞体提供碘来控制碘的浓度。分压控制单元（400）控制提供给心轴芯体的碘的压力。数据存储单元（500）实时存储转换后的数据。

75. 发明公开

KR1020120102969A 우수한 내식성 및 고강도를 가지는 지르코늄합금의 제조방법 有权
标题翻译：具有优异耐腐蚀性和高强度的ZIRCONIUM合金制造方法
公开(公告)号：KR1020120102969A
公开(公告)日：2012-09-19
申请号：KR1020110020921
申请日：2011-03-09
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 김현길 , 박상윤 , 정용환 , 최병권 , 박동준 , 정양일 , 박정용
IPC分类号： C22F1/18 , B21J5/00 , B21K1/00
CPC分类号： C22F1/186 , B21J5/00 , C22C16/00 , G21C21/00
摘要： PURPOSE: A method for preparing zirconium alloy is provided to obtain superior corrosion resistance and high strength by reducing the average size of precipitation and using the pinning effect of fine precipitation. CONSTITUTION: A method for preparing zirconium alloy comprises the steps of: melting a zirconium alloy composition and making ingot(S100), forging the ingot in a B-phase region(S200), performing solution treatment of the ingot in a B-phase region and quenching the solution(S300), hot working the B-quenched ingot(S400), performing first vacuum heat treatment of the semi-product, cooling the semi-product below 100 °C, and then performing second vacuum heat treatment of the semi-product(S500), cold working the semi-product(S600), performing first vacuum heat treatment of the semi-product, cooling the semi-product below 100 °C, and then performing second vacuum heat treatment of the semi-product(S700), cold working the semi-product(S800), and performing the final heat treatment of the semi-product(S900). [Reference numerals] (S100) Ingot making step(step 1); (S200) Β-forging step(step 2); (S300) Β-quenching step(step 3); (S400) Hot working step(step 4); (S500) First and second heat treatment step(step 5); (S600) Cold working step(step 6); (S700) First and second heat treatment step(step 7); (S800) Cold working step(step 8); (S900) Final heat treatment step(step 9)
摘要翻译：目的：提供一种制备锆合金的方法，通过降低沉淀的平均尺寸和使用精细沉淀的钉扎效应，获得优异的耐腐蚀性和高强度。构成：制备锆合金的方法包括以下步骤：将锆合金组合物熔化并制成锭（S100），在B相区域锻造锭（S200），在B相区域中进行锭的固溶处理并淬火溶液（S300），对B淬火锭进行热加工（S400），对半成品进行第一次真空热处理，将半成品冷却至100℃以下，然后进行第二次真空热处理 - 产品（S500），冷加工半成品（S600），对半成品进行第一次真空热处理，冷却半成品低于100℃，然后对半成品进行第二次真空热处理（ S700），冷加工半成品（S800），进行半成品（S900）的最终热处理。（附图标记）（S100）锭制造步骤（步骤1）; （S200）＆Beta;锻造步骤（步骤2）; （S300）＆Beta;淬火步骤（步骤3）; （S400）热加工步骤（步骤4）; （S500）第一和第二热处理步骤（步骤5）; （S600）冷加工工序（工序6）。（S700）第一和第二热处理步骤（步骤7）; （S800）冷加工步骤（步骤8）; （S900）最终热处理工序（工序9）

76. 发明公开

KR1020100128871A 고강도 및 우수한 내식성을 확보한 핵연료 안내관 및 계측관용 지르코늄 합금의 제조방법 有权
标题翻译：用于燃料导管和制造具有高强度和优异耐腐蚀性的测量管的制造方法
公开(公告)号：KR1020100128871A
公开(公告)日：2010-12-08
申请号：KR1020090047526
申请日：2009-05-29
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 김현길 , 정용환 , 박상윤 , 이명호 , 최병권 , 박정용 , 정양일 , 박동준
IPC分类号： G21C3/30 , C22C16/00
CPC分类号： G21C21/00 , C22C16/00 , C22F1/18 , C22F1/186 , G21C3/07 , G21C21/02 , Y02E30/40
摘要： PURPOSE: A process of manufacturing zirconium alloy for a fuel guide tube and a measuring tube having high strength and excellent corrosion resistance are provided to obtain the profitability in manufacturing by simplifying the three step manufacturing process to the two step manufacturing process. CONSTITUTION: The TREX shell(2) which is the semi-product for the zircaloy tube production is cooling-processed primarily. The middle heat treatment for the TREX shell is implemented. The intermediate product which is intermediate-heat treated is cooling-processed secondarily. The final heat-treatment process is implemented.
摘要翻译：目的：提供一种用于制造用于燃料导管的锆合金和具有高强度和优异的耐腐蚀性的测量管的方法，以通过简化两步制造过程的三步制造过程来获得制造的盈利能力。构成：作为锆石管生产的半成品的TREX外壳（2）主要进行冷却处理。实施TREX外壳的中间热处理。中间热处理的中间产物进行二次冷却处理。实施最终的热处理过程。

77. 发明公开

KR1020090117414A 보호성 산화막을 형성하는 핵연료피복관용 지르코늄 합금조성물, 이를 이용하여 제조한 지르코늄 합금 핵연료피복관및 이의 제조방법 有权
标题翻译：用于形成保护氧化物的核燃料层的ZIRCONIUM合金，使用其制备的ZIRCONIUM合金核燃料层及其制备方法
公开(公告)号：KR1020090117414A
公开(公告)日：2009-11-12
申请号：KR1020080043446
申请日：2008-05-09
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 박정용 , 정용환 , 박상윤 , 이명호 , 최병권 , 김현길 , 정양일
IPC分类号： G21C3/07 , G21C3/00
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21C21/02 , Y02E30/40
摘要： PURPOSE: A zirconium alloy composition for a nuclear fuel cladding tube, the zirconium alloy nuclear fuel cladding tube using the same, and a manufacturing method thereof are provided to maintain high corrosion resistance for a long time by forming a protective oxide layer in a light water or heavy water reactor. CONSTITUTION: An ingot is made by cooling a zirconium alloy composition. The ingot is forged at the temperature of 1000 to 1200 degrees centigrade. The forged ingot is cooled with the cooling speed of 300 to 400 °C/s. The cooled ingot is extruded from the temperature of 600 to 640 degrees centigrade. An extruded material is thermally processed for two to four hours at the temperature of 570 to 610 degrees centigrade. A zirconium alloy nuclear cladding tube is made by thermally processing the extruded material for 3 to 10 hours at the temperature of 570 to 610 degrees centigrade.
摘要翻译：目的：提供一种用于核燃料包壳管的锆合金组合物，使用其的锆合金核燃料包覆管及其制造方法，以通过在轻水中形成保护性氧化物层来长期保持高耐腐蚀性或重水反应堆。构成：通过冷却锆合金组合物制成锭。铸锭在1000至1200摄氏度的温度下锻造。锻造的铸锭以300〜400℃/ s的冷却速度冷却。冷却的铸锭从600至640摄氏度的温度挤出。将挤出的材料在570至610摄氏度的温度下热处理2至4小时。通过在570〜610℃的温度下对挤压材料进行热处理3〜10小时来制造锆合金核包层管。

78. 发明公开

KR1020090093483A 다양한 산소화합물 및 석출상의 제어를 통한 우수한내식성을 갖는 지르코늄 합금 조성물 및 이의 제조방법 有权
标题翻译：通过各种金属氧化物和降解剂的控制具有优异的耐腐蚀性的锆合金组合物及其制备方法
公开(公告)号：KR1020090093483A
公开(公告)日：2009-09-02
申请号：KR1020080019028
申请日：2008-02-29
申请人： 한국원자력연구원
发明人： 김현길 , 정용환 , 최병권 , 박상윤 , 이명호 , 박정용 , 김준환
IPC分类号： C22C16/00
CPC分类号： C22C16/00
摘要： A zirconium alloying composition and a manufacturing method of the same are provided to have the excellent corrosion resistance by controlling the size of the deposition phase of the zircaloy. A zirconium alloying composition manufacturing method comprises followings. The mixture of the zirconium alloy composition element is dissolved and the ingot is manufactured. The manufactured ingot is forged in a beta domain. The forged ingot is cooled quickly after the solution treatment post-baking in the beta domain. The cooled ingot is heat-processed and extruded. The initial annealing is performed about the extruded intermediate product. The cold processing and middle heat treatment are repeated about the heat-treated intermediate product with the several occasions. The heat-treatment is performed at 560~650 °C for 15~40 minutes. The initial annealing is performed at 550~650 °C for 1~5 hours. The final heat-treatment is performed at 450~580°C for 2~10 hours.
摘要翻译：通过控制锆石的沉积相的尺寸，提供锆合金组合物及其制造方法以具有优异的耐腐蚀性。锆合金组合物的制造方法如下。溶解锆合金组成元素的混合物，制造锭。制造的锭在beta域中锻造。在β结构域后烘烤后的溶液处理后，锻造的铸锭被快速冷却。冷却的锭子经过热处理和挤压。对挤出的中间产物进行初始退火。多次对热处理的中间产品进行冷加工和中间热处理。热处理在560〜650℃进行15〜40分钟。初始退火在550〜650℃下进行1〜5小时。最终热处理在450〜580℃进行2〜10小时。

79. 发明公开

KR1020080084909A 우수한 내식성을 갖는 고농도 철 함유 지르코늄 합금 조성물 및 이의 제조방법 有权
标题翻译：具有优异耐腐蚀性的高含量的ZIRCONIUM合金组合物及其制备方法
公开(公告)号：KR1020080084909A
公开(公告)日：2008-09-22
申请号：KR1020080085103
申请日：2008-08-29
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 정용환 , 김현길 , 박상윤 , 이명호 , 최병권 , 백종혁 , 박정용 , 김준환
IPC分类号： C22C16/00
CPC分类号： C22C16/00 , C22C2202/00 , C22F1/186
摘要： A high concentration Fe-contained zirconium alloy composition comprising Zr, Fe, Cr, O and Sn having excellent corrosion resistance and a manufacturing method thereof are provided, wherein the high concentration Fe-contained zirconium alloy composition can be used as material of nuclear fuel cladding tubes, spacer grids, and structures used in higher burnup and longer cycle operation. A high concentration Fe-contained zirconium alloy composition having excellent corrosion resistance comprises: 0.5 to 1.0% by weight of iron; 0.25 to 0.5% by weight of chromium; 0.06 to 0.18% by weight of oxygen; 0.2 to 0.5% by weight of tin; and the balance of zirconium. The zirconium alloy composition comprises: 0.54 to 0.8% by weight of iron; 0.27 to 0.40% by weight of chromium; 0.1 to 0.15% by weight of oxygen; 0.2 to 0.5% by weight of tin; and the balance of zirconium. The zirconium alloy composition comprises 0.1 to 0.3% by weight of niobium.
摘要翻译：提供了包含具有优异耐腐蚀性的Zr，Fe，Cr，O和Sn的高浓度含铁锆合金组合物及其制造方法，其中高浓度Fe含量的锆合金组合物可用作核燃料包覆材料管，隔离栅和用于较高燃耗和较长循环运行的结构。具有优异耐腐蚀性的高浓度含铁锆合金组合物包括：0.5-1.0重量％的铁; 0.25〜0.5重量％的铬; 0.06〜0.18重量％的氧气; 0.2〜0.5重量％的锡; 和锆的平衡。锆合金组合物包含：0.54至0.8重量％的铁; 0.27〜0.40重量％的铬; 0.1〜0.15重量％的氧气; 0.2〜0.5重量％的锡; 和锆的平衡。锆合金组合物含有0.1〜0.3重量％的铌。

80. 发明公开

KR1020080074568A 우수한 내식성을 갖는 고농도 철 함유 지르코늄 합금조성물 및 이의 제조방법 无效
标题翻译：具有优异耐腐蚀性的高含量的ZIRCONIUM合金组合物及其制备方法
公开(公告)号：KR1020080074568A
公开(公告)日：2008-08-13
申请号：KR1020070013871
申请日：2007-02-09
申请人： 한국원자력연구원 , 한국수력원자력 주식회사
发明人： 정용환 , 김현길 , 박상윤 , 이명호 , 최병권 , 백종혁 , 박정용 , 김준환
IPC分类号： C22C16/00 , C21D8/00
CPC分类号： G21C3/07 , Y02E30/40
摘要： A high Fe contained zirconium alloy composition having excellent corrosion resistance and a manufacturing method thereof are provided to manufacture a zirconium alloy composition through repeat cold working and middle heat treatment processes so as to use the zirconium alloy composition as a nuclear fuel coating pipe, a support lattice, and a material for a structure. A high Fe contained zirconium alloy composition having excellent corrosion resistance contains at least one element selected from a group having 0.05 to 1.0 weight% of iron, 0.25 to 0.5 weight% of chrome, 0.06 to 0.18 weight% of oxygen, 0.2 to 0.5 weight% of tin, 0.1 to 0.3 weight% of niobium, and 0.05 to 0.3 weight% of copper, and the remaining zirconium. Ingot is forged in a beta area. The ingot is processed in the beta area by solution heat and quenched. The quenched ingot is extruded. An extruded body is heat-treated first. A zirconium alloy composition is manufactured by repeat cold working and middle heat treatment processes. The zirconium alloy composition is heat-treated last.
摘要翻译：提供具有优异耐腐蚀性的高Fe含量的锆合金组合物及其制造方法，以通过重复冷加工和中间热处理工艺制造锆合金组合物，以便使用锆合金组合物作为核燃料涂覆管，晶格和结构材料。具有优异耐腐蚀性的高含铁锆合金组合物含有至少一种选自铁，0.05至1.0重量％，0.25至0.5重量％的铬，0.06至0.18重量％的氧，0.2至0.5重量％的锡，0.1〜0.3重量％的铌和0.05〜0.3重量％的铜，以及剩余的锆。锭在β区被伪造。该锭在β区域通过溶解热处理并淬火。淬火锭被挤出。首先对挤压体进行热处理。通过重复冷加工和中间热处理工艺制造锆合金组合物。最后对锆合金组合物进行热处理。

你已经成功收藏专利！

检索式保存成功!

IPRDB

热门服务

关于我们

友情链接

联系方式