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公开(公告)号：US09653188B2
公开(公告)日：2017-05-16
申请号：US13747685
申请日：2013-01-23
Applicant: Korea Atomic Energy Research Institute
Inventor： Young Woo Rhee , Dong-Joo Kim , Jong-Hun Kim , Jae-Jo Yang , Keon-Sik Kim , Yang-Hyun Koo
Abstract: A fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same are provided, in which the fabrication method includes adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO2), plutonium dioxide (PuO2) and thorium dioxide (ThO2) and mixing the same (step 1), compacting the mixed powder of step 1 into compacts (step 2), and sintering the compacts of step 2 under hydrogen atmosphere (step 3). According to the fabrication method, sintering can be performed under hydrogen atmosphere at a temperature lower than the hydrogen atmosphere sintering that is conventionally applied in the nuclear fuel sintered pellet mass production, by adding sintering additives such as manganese oxide or the like.
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2.发明授权Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof 有权用于核燃料包层的锆合金通过减少合金元素的量而具有优异的耐腐蚀性和使用其制备锆合金核燃料包层的方法公开(公告)号：US09202597B2
公开(公告)日：2015-12-01
申请号：US13747614
申请日：2013-01-23
Inventor： Jeong-Yong Park , Byoung-Kwon Choi , Hyun Gil Kim , Sang Yoon Park , Yang-Il Jung , Dong Jun Park , Yang-Hyun Koo
Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.
Abstract translation: 公开了一种通过减少合金元素量的具有良好耐腐蚀性的核燃料包层锆合金，以及使用该锆合金制备锆合金核燃料包层的方法。 锆合金含有0.2〜0.5重量％的铌（Nb）; 0.2〜0.6重量％的铁（Fe）; 0.3〜0.5重量％的铬（Cr）; 0.1〜0.15重量％的氧（O）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 铌，铁和铬的总量为1.1〜1.2重量％。 可以在事故条件和反应堆的正常运行条件下确认核燃料包层的良好的抗氧化性，从而提高经济可行性和安全性。
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公开(公告)号：US10102929B2
公开(公告)日：2018-10-16
申请号：US14591498
申请日：2015-01-07
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor： Dong-Joo Kim , Young Woo Rhee , Keon-Sik Kim , Jong-Hun Kim , JangSoo Oh , Jae-Ho Yang , Yang-Hyun Koo
Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.
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4.发明授权Zirconium alloy for improving resistance to oxidation at very high temperature and fabrication method thereof 有权在非常高的温度下提高耐氧化性的锆合金及其制造方法公开(公告)号：US09421740B2
公开(公告)日：2016-08-23
申请号：US13670515
申请日：2012-11-07
Inventor： Kun-Woo Song , Yang-Hyun Koo , Byoung-Kwon Choi , Il-Hyun Kim , Hyun-Gil Kim , Yang-Il Jung , Dong Jun Park , Jeong-Yong Park
IPC: C23C4/04 , C23C4/08 , C23C4/12 , B32B15/01 , C23C4/18 , C23C4/02 , C22C16/00 , C22F1/18 , G21C3/07 , G21C3/30
CPC classification number: B32B15/01 , C22C16/00 , C22F1/186 , C23C4/02 , C23C4/08 , C23C4/134 , C23C4/18 , G21C3/07 , G21C3/30 , Y02E30/40 , Y10T428/12674 , Y10T428/12812
Abstract: A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved.
Abstract translation: 提供了用于核燃料组件的锆合金，其提供增加的抗氧化和腐蚀性，并且还改善了与母体材料的接合，因为诸如硅（Si）或铬（Cr）的纯金属材料被均匀地涂覆在 母材通过等离子喷涂。 由于用于在锆合金上涂覆纯金属材料的等离子体喷涂不需要真空设备，并且由于涂覆产品的形状也不受限制，因此当将组分的表面均匀地处理如4 m形管子或间隔手柄装置，其形状非常复杂。 此外，由于涂覆的锆合金在事故和正常使用条件下在紧急情况下具有优异的抗氧化和耐腐蚀性，因此提高了核燃料的经济性和安全性。
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公开(公告)号：US10043595B2
公开(公告)日：2018-08-07
申请号：US14060432
申请日：2013-10-22
Inventor： Keon-Sik Kim , Yang-Hyun Koo , Jong-Hun Kim , JangSoo Oh , Young Woo Rhee , Dong-Joo Kim , Jae-Ho Yang
CPC classification number: G21C3/044 , G21C3/045 , G21C3/16 , G21C3/17 , G21C3/58 , G21C3/62 , G21C21/02 , Y02E30/38
Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 μM (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.
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Patent Agency Ranking
6.发明授权公开(公告)号：US09679666B2
公开(公告)日：2017-06-13
申请号：US14061662
申请日：2013-10-23
Inventor： Keon-Sik Kim , Yang-Hyun Koo , Jong-Hun Kim , JangSoo Oh , Young Woo Rhee , Dong-Joo Kim , Jae-Ho Yang
Abstract: Disclosed is a uranium dioxide nuclear fuel pellet, which includes metallic microcell partitions having a high protection capacity for fission products and a high thermal conductivity simultaneously. These metal microcell partitions are arranged in the nuclear fuel pellet to trap fission products. Further disclosed is a method of making the uranium dioxide nuclear fuel pellet. The method includes providing a mixture of uranium dioxide powder and additive powder of Cr-containing compound or Mo-containing compound; compressing the powder mixture to form a green pellet; and then sintering the green pellet under reducing gas environment to form the metallic microcell partitions.
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公开(公告)号：US09136023B2
公开(公告)日：2015-09-15
申请号：US13747614
申请日：2013-01-23
Inventor： Jeong-Yong Park , Byoung-Kwon Choi , Hyun Gil Kim , Sang Yoon Park , Yang-Il Jung , Dong Jun Park , Yang-Hyun Koo
Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.
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8.发明授权Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same 有权在反应堆事故状态下具有优异的抗氧化性的核燃料包层的锆合金，使用它们制备的锆合金核燃料包层及其制备方法公开(公告)号：US09099205B2
公开(公告)日：2015-08-04
申请号：US13747042
申请日：2013-01-22
Inventor： Jeong-Yong Park , Hyun Gil Kim , Byoung-Kwon Choi , Sang Yoon Park , Yang-Il Jung , Dong Jun Park , Yang-Hyun Koo
Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.
Abstract translation: 公开了一种用于核燃料包层的锆合金，其在反应堆事故条件下具有良好的抗氧化性，通过使用它制备的锆合金核燃料包覆层及其制备方法。 锆合金含有1.0〜1.2重量％的铌（Nb）; 选自锡（Sn），铁（Fe）和铬（Cr）中的至少一种元素; 0.02〜0.1重量％的铜（Cu）; 0.1〜0.15重量％的氧（O）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 Sn的量为0.1〜0.3重量％，Fe的量为0.3〜0.8重量％，Cr的含量为0.1〜0.3重量％。 可以在事故条件以及反应堆的正常运行条件下确认核燃料包层的良好的抗氧化性，从而提高经济效率和安全性。
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公开(公告)号：US10808307B2
公开(公告)日：2020-10-20
申请号：US15610533
申请日：2017-05-31
Applicant: Korea Atomic Energy Research Institute
Inventor： Hyun Gil Kim , Il Hyun Kim , Yang-Il Jung , Dong Jun Park , Jung Hwan Park , Jeong-Yong Park , Yang-Hyun Koo
Abstract: The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.
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10.发明授权Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a severe reactor operation condition and methods of preparing a zirconium alloy nuclear cladding by using thereof 有权用于核燃料包层的锆合金在严格的反应器操作条件下具有优异的抗氧化性，以及通过使用它制备锆合金核包层的方法公开(公告)号：US09111650B2
公开(公告)日：2015-08-18
申请号：US13747763
申请日：2013-01-23
Inventor： Jeong-Yong Park , Yang-Il Jung , Hyun Gil Kim , Byoung-Kwon Choi , Sang Yoon Park , Dong Jun Park , Yang-Hyun Koo
Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety.
Abstract translation: 公开了一种在严格的反应器运行条件下具有良好的抗氧化性的核燃料包覆用锆合金，以及通过使用它们制备锆合金核燃料包层的方法。 锆合金含有1.8〜2.0重量％的铌（Nb）; 选自铁（Fe），铬（Cr）和铜（Cu）中的至少一种元素; 0.1〜0.15重量％的氧（O）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 Fe的量为0.1〜0.4重量％，Cr的含量为0.05〜0.2重量％，Cu的含量为0.03〜0.2重量％。 在反应堆的事故状态以及反应堆的正常运行状态下，在严格的反应堆操作条件下，可以确认核燃料包层的良好的抗氧化性，从而提高经济效率和安全性。
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