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61.发明授权Method of producing heat-resistant high chromium ferritic/martensitic steel 有权一种用于制造耐热富含铬的铁素体 - 马氏体钢过程
公开(公告)号：EP1544312B1
公开(公告)日：2010-09-15
申请号：EP04078288.0
申请日：2004-12-03
发明人： Ryu, Woo Seog , Kim, Sung Ho , Song, Byoung Jun , Hong, Jun Hwa
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62.发明公开Nuclear fuel body including tungsten network and method of manufacturing the same 有权HerstellungsverfahrenfüreinenKernbrennstoffkörpermit einem Wolframnetzwerk
公开(公告)号：EP1424701A1
公开(公告)日：2004-06-02
申请号：EP03292513.3
申请日：2003-10-10
发明人： Song, Kun Woo , Yang, Jae Ho , Kim, Keon Sik , Kang, Ki Won , Kim, Jong Hun , Jung, Youn Ho
IPC分类号： G21C3/62
CPC分类号： G21C3/623 , G21Y2002/104 , G21Y2004/10 , Y02E30/38
摘要： The present invention relates to a nuclear fuel body comprising tungsten network and a method for manufacturing the same, more particularly, a nuclear fuel body in which tungsten network is continuously formed over the entire or some parts of a sintered body and a method for manufacturing the same. The sintered body in the nuclear fuel body of the present invention contains tungsten network having excellent heat conductivity, leading to the enhancement of heat conductivity of the nuclear fuel sintered body itself with decreasing the temperature of the nuclear fuel, so that it can contribute to the improvement in safety and performance of nuclear fuel.
摘要翻译： 本发明涉及一种包括钨网络的核燃料体及其制造方法，更具体地说，涉及在烧结体的全部或部分上连续形成钨网络的核燃料体及其制造方法 相同。 本发明的核燃料体中的烧结体含有具有优异导热性的钨网络，导致核燃料烧结体本身的导热性随着核燃料温度的降低而提高，从而可以有助于 提高核燃料的安全和性能。
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63.发明公开Zirconium alloy having excellent corrosion resistance and mechanical properties and method for preparing nuclear fuel cladding tube by zirconium alloy 有权与锆合金包壳管的改进的耐腐蚀性和改进的机械性能和生产方法，用于核反应堆燃料棒锆合金
公开(公告)号：EP1256634A1
公开(公告)日：2002-11-13
申请号：EP01309314.1
申请日：2001-11-02
发明人： Jeong, Yong Hwan , Baek, Jong Hyuk , Choi, Byoung Kwon , Park, Sang Yoon , Nam, Cheol , Jung, Youn Ho , Lee, Myung Ho
摘要： The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a=0.05-0.4 wt%, b=0.3-0.7 wt%, c=0.1-0.4 wt%, d=0-0.2 wt% and e=0.01-0.2 wt%, provided that Nb+Sn=0.35-1.0 wt%), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at β phase range, β-quenching the forged ingot at 1015-1075 °c, hot-working the quenched ingot at 600-650 °C, cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing and final vacuum annealing the worked ingot at 460-540 °C, which can be applied to the core components in a light water and a heavy water atomic reactor type nuclear power plant.
摘要翻译： 本发明涉及一种具有优异的耐腐蚀性和机械性能以及用于通过锆合金制备核燃料包覆管的方法的锆合金。 更格外地，本发明涉及一种锆合金Zr的含有ANB-AAS-CFE DCR ECU（A = 0.05-0.4重量％，B = 0.3〜0.7％（重量），C = 0.1-0.4％（重量），D = 0-0.2％（重量）和e = 0.01〜0.2重量％，提供确实的Nb + SN = 0.35-1.0重量％），以及制备锆合金的核燃料包覆管，包括熔化的金属混合物，其包含的一个方法 锆和合金元素，以获得铸块，锻造在β相范围的锭，β--quenching锻造锭在1015至1075年℃，热加工在600-650℃下骤冷的锭，冷加工热加工锭 计划在三到五遍，与中间真空退火和最终真空退火在460-540℃下的加工锭，其可以在光水和重水原子反应堆类型核电被施加到核心组件。
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公开(公告)号：EP4462447A1
公开(公告)日：2024-11-13
申请号：EP23737330.3
申请日：2023-01-02
摘要： There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.
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65.发明公开
公开(公告)号：EP4354241A1
公开(公告)日：2024-04-17
申请号：EP21945288.5
申请日：2021-11-15
申请人： Korea Hydro & Nuclear Power Co., Ltd , ATG Co., Ltd. , Industry-Academic Cooperation Foundation Gyeongsang National University
发明人： KIM, Min Ho , KIM, Dae Woong , YE, Song Hae , LEE, Won Kyu , KIM, Ju Sik , MOON, Byeong Suk , KANG, Sin Gyu , CHOI, Byeong Keun , YU, Hyeon Tak
摘要： A vibration measurement error determination method according to an embodiment of the present invention comprises: a vibration data acquisition step for acquiring vibration data by measuring a vibration generated in a structure; a first determination step for determining, on the basis of a preset error data selection rule, whether the vibration data is data generated by a measurement error; a second determination step for using a machine-learning algorithm to determine whether the vibration data is data generated by a measurement error; and a final determination step for determining, on the basis of the results determined in the first determination step and the second determination step, whether the vibration data is data generated by a measurement error.
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66.发明公开
公开(公告)号：EP4290531A1
公开(公告)日：2023-12-13
申请号：EP22749887.0
申请日：2022-01-18
发明人： SHIN, Hye Young
摘要： The present invention relates to an integrated nuclear reactor system including a double containment structure using liquid nitrogen, the nuclear reactor system comprising: a reactor vessel; a reactor core disposed in the reactor vessel; a steam generator disposed in the reactor vessel and located above the reactor core; a first containment vessel surrounding the reactor vessel with a first space interposed therebetween; a second containment vessel surrounding the first containment vessel with a second space interposed therebetween; and a liquid nitrogen supply unit supplying liquid nitrogen into the second space.
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67.发明公开
公开(公告)号：EP4235701A1
公开(公告)日：2023-08-30
申请号：EP21883291.3
申请日：2021-10-21
发明人： CHUNG, Sunghwan , KIM, Yongdeog , KIM, Kiyoung , KIM, Taehyeon , LEE, Donghee , SON, Jinwon , LEE, Dong-Gyu , JUNG, In-Su , YANG, Ke-Hyung , JANG, Jun-Sang , KIM, Tae-Su
摘要： The present invention relates to a cutting apparatus for a fuel basket containing spent nuclear fuel in a heavy water reactor and, more particularly, to a cutting apparatus for a fuel basket containing spent nuclear fuel in a heavy water reactor, which enables the spent nuclear fuel contained inside to be withdrawn without damage through welding bead cutting rather than through-cutting, and enables cutting chips generated during a cutting operation to be neatly and easily recovered without scattering on the bottom of a storage tank. To this end, the present invention provides a cutting apparatus for a fuel basket containing spent nuclear fuel in a heavy water reactor, the apparatus comprising: a base; a vertical support installed on one side of the base; a rotary table installed to reciprocate between the one side and the other side of the base, and to rotate horizontally on the base; a horizontal support installed to extend from the upper end of the vertical support toward the rotary table in a horizontal direction; a side cutting means installed on the vertical support and protruding toward the rotary table so as to cut a side welding bead of a fuel basket mounted on the rotary table; and an upper cutting means installed on the horizontal support and protruding toward the rotary table so as to cut an upper welding bead of the fuel basket mounted on the rotary table.
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公开(公告)号：EP4224124A1
公开(公告)日：2023-08-09
申请号：EP21875981.9
申请日：2021-09-27
发明人： LEE, Seung Chan
IPC分类号： G01F23/296 , G01D11/24 , G01D11/30 , G21C19/07
摘要： A water level measurement system according to an embodiment includes a support pipe installed in a water tank filled with a fluid to measure a water level and extending in a depth direction of the water tank, a support rod disposed on one side of the support pipe based on a central axis of the support pipe and extending in the depth direction of the water tank, a plurality of ultrasonic probes attached to the support rod and generating ultrasonic waves, and a water level calculator connected to the plurality of ultrasonic probes and calculating the water level of the water tank.
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公开(公告)号：EP4198843A1
公开(公告)日：2023-06-21
申请号：EP21856122.3
申请日：2021-08-03
发明人： LEE, Seung Chan
IPC分类号： G06N20/00
摘要： An artificial intelligence (Al) feedback method includes: providing input1 and input2, providing an initial condition for a popularity frequency value or ranking value of information related to input 2 from input 1, generating a two-dimensional (2D) information table from the initial condition, adding the popularity frequency value or ranking value to corresponding coordinates in the 2D information table and matching knowledge, generating a 2D pseudolinear transformation table from the 2D information table, performing pseudolinear transformation multiple times to form a 2D unique characteristic table and deriving information of coordinates whose characteristic vector is not changed as a deep truth value, and organizing and storing a context of knowledge formed by connecting the deep truth value by category.
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公开(公告)号：EP4167251A1
公开(公告)日：2023-04-19
申请号：EP21821656.2
申请日：2021-06-10
发明人： AHN, Hyoyoung
摘要： A reactor core for load following operation includes a reactor core body, a plurality of load-following control rods that are inserted into the reactor core body in an axial direction in response to an output set for the load following operation, overlap each other in the axial direction, and are simultaneously raised and lowered, and a first power axial offset control rod that is spaced apart from the plurality of load-following control rods in a plane, has an end portion positioned below a center of the reactor core body in the axial direction, and is raised and lowered only below the center of the reactor core body in a direction to compensate for a fluctuation in a power axial offset due to the insertion of the plurality of load-following control rods.
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