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公开(公告)号:US07504079B2
公开(公告)日:2009-03-17
申请号:US11483711
申请日:2006-07-10
申请人: Younghwan Kim , Jisup Yoon , Jaehoo Jung , Donghee Hong , Jaehyun Jin
发明人: Younghwan Kim , Jisup Yoon , Jaehoo Jung , Donghee Hong , Jaehyun Jin
CPC分类号: G21C19/48 , Y02W30/884 , Y10S422/903
摘要: A vol-oxidizer of spent nuclear fuel, the spent nuclear fuel is injected to a reaction portion, the reaction portion is connected to a driving portion and oxidizes the spent nuclear fuel by rotating and back-rotating the spent nuclear fuel. The oxidized powder of the spent nuclear fuel is gathered in a discharge portion located in a lower portion of the reaction portion. By providing minute powder particles for recycling and a post process of the spent nuclear fuel, even though a size of an apparatus is small, processing a large amount is possible. Time required for oxidation can be reduced, and the powder is readily discharged by gravity since the apparatus is vertically configured.
摘要翻译: 废核燃料的挥发氧化剂,将废核燃料注入到反应部分中,反应部分连接到驱动部分,并通过旋转和反向旋转废核燃料来氧化废核燃料。 废核燃料的氧化粉末聚集在位于反应部分下部的排放部分中。 通过提供用于回收的微粉末颗粒和废核燃料的后处理,即使装置的尺寸小,也可以大量处理。 可以减少氧化所需的时间,并且由于该装置是竖直构造,所以粉末容易被重力排出。
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公开(公告)号:US20070110640A1
公开(公告)日:2007-05-17
申请号:US11483711
申请日:2006-07-10
申请人: Younghwan Kim , Jisup Yoon , Jaehoo Jung , Donghee Hong , Jaehyun Jin
发明人: Younghwan Kim , Jisup Yoon , Jaehoo Jung , Donghee Hong , Jaehyun Jin
IPC分类号: B01J19/00
CPC分类号: G21C19/48 , Y02W30/884 , Y10S422/903
摘要: A vol-oxidizer of spent nuclear fuel, the spent nuclear fuel is injected to a reaction portion, the reaction portion is connected to a driving portion and oxidizes the spent nuclear fuel by rotating and back-rotating the spent nuclear fuel. The oxidized powder of the spent nuclear fuel is gathered in a discharge portion located in a lower portion of the reaction portion. By providing minute powder particles for recycling and a post process of the spent nuclear fuel, even though a size of an apparatus is small, processing a large amount is possible. Time required for oxidation can be reduced, and the powder is readily discharged by gravity since the apparatus is vertically configured.
摘要翻译: 废核燃料的挥发氧化剂,将废核燃料注入到反应部分中,反应部分连接到驱动部分,并通过旋转和反向旋转废核燃料来氧化废核燃料。 废核燃料的氧化粉末聚集在位于反应部分下部的排放部分中。 通过提供用于回收的微粉末颗粒和废核燃料的后处理,即使装置的尺寸小,也可以大量处理。 可以减少氧化所需的时间,并且由于该装置是竖直构造,所以粉末容易被重力排出。
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公开(公告)号:US20240320522A1
公开(公告)日:2024-09-26
申请号:US18579006
申请日:2022-07-18
发明人: Seung Chan LEE
IPC分类号: G06N5/022
CPC分类号: G06N5/022
摘要: An artificial intelligence (AI) feedback system is provided. The AI feedback system includes: a script extractor/executor receiving input 1, which includes basic materials for learning, and input 2, which includes key contents for learning, and generating initial conditions for popularity frequency values or ranking values of information related to input 2 from input 1; an AI connected to the script extractor/executor, the AI generating a two-dimensional (2D) information table in a matrix form with both axes for keywords and key information, respectively, based on popularity frequency values or ranking values derived from the initial conditions, adding the popularity frequency values or ranking values to corresponding coordinates of the 2D information table, and matching acquired knowledge to the corresponding coordinates; an output unit connected to the AI and outputting deep truth values derived by the AI from the 2D information table; and a repository connected to the AI, organizing and storing, by category, the context of knowledge formed by linking the deep truth values derived by the AI.
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4.
公开(公告)号:US20240271990A1
公开(公告)日:2024-08-15
申请号:US18568732
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: Min Ho KIM , Dae Woong KIM , Song Hae YE , Won Kyu LEE , Ju Sik KIM , Byeong Suk MOON , Sin Gyu KANG , Byeong Keun CHOI , Hyeon Tak YU
IPC分类号: G01H1/00
CPC分类号: G01H1/003
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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公开(公告)号:US20240094686A1
公开(公告)日:2024-03-21
申请号:US18257077
申请日:2022-01-19
发明人: Dae Seung PARK
CPC分类号: G05B13/048 , G05B23/0283
摘要: An operation prediction system for multiple devices, according to one embodiment of the present invention, comprises: a control unit; a first device of which the operation state is changed by being controlled by the control unit; a second device which is linked to the first device; a prediction input unit which receives a prediction input which is an input for predicting the operation state to be changed of the first device; and a state prediction unit which predicts operation prediction information including information on the operation state of the first device, which is to be changed by the controlling of the control unit, and information on the impact on the second device as a result of the operation state to be changed of the first device.
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6.
公开(公告)号:US20240034646A1
公开(公告)日:2024-02-01
申请号:US18258425
申请日:2022-03-04
发明人: Cho Rong KIM , Hak Soo KIM , Jeong Ju KIM , Sang Ho LEE , Eun Hee HONG , Ji Eun PARK , Ka Hee JEONG
IPC分类号: C02F1/32
CPC分类号: C02F1/325 , C02F2101/30
摘要: Provided is a UV reaction apparatus for treating waste liquid caused by system decontamination in a nuclear power plant. The UV reaction apparatus comprises a UV irradiation unit for irradiating UV light as a bar-shaped body; and a transit unit accommodating the UV irradiation unit therein, and for passing organic waste liquid to be irradiated with the UV light, wherein the transit unit comprises, an input unit, into which the organic waste liquid is input a discharge unit, through which the organic waste liquid is discharged, and an intermediate unit located between the input unit and the discharge unit, and in which the UV irradiation unit is located.
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公开(公告)号:US11848114B2
公开(公告)日:2023-12-19
申请号:US17429031
申请日:2020-02-14
发明人: Ju-Young Yoon , Young Hwan Hwang , Mi-Hyun Lee , Cheon-Woo Kim
IPC分类号: G21D1/00 , G21C13/024 , G21C19/00
CPC分类号: G21D1/003 , G21C13/024 , G21C19/00
摘要: An underwater decommissioning method of a nuclear facility including a nuclear reactor pressure vessel and bio-protective concrete comprising a cavity in which the nuclear reactor pressure vessel is positioned is disclosed. The method includes: (a) lifting the nuclear reactor pressure vessel above the cavity; (b) forming an insertion part in the bio-protective concrete adjacent to the cavity, filling the insertion part with water, and installing a support part on a bottom surface of the insertion part; (c) inserting the nuclear reactor pressure vessel in the insertion part and mounting a lower portion of the nuclear reactor pressure vessel on the support part; and (d) repeatedly cutting portions of the nuclear reactor pressure vessel mounted on the support part by using a cutting device in an underwater position. The method allows performing cutting operations in the water, and thus, it is possible to prevent radiation exposure due to occurrence of dust.
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公开(公告)号:US11830633B2
公开(公告)日:2023-11-28
申请号:US17430405
申请日:2020-02-10
发明人: Seok-Ju Hwang , Young Hwan Hwang , Mi-Hyun Lee , Cheon-Woo Kim
CPC分类号: G21D1/003 , B26D1/56 , B26D2210/00
摘要: A method for decommissioning a heavy water reactor facility includes: opening an upper part of the calandria vault; inserting a support device into an inner part of the calandria vault through the upper part of the calandria vault to support the main shell of the calandria; cutting between the main shell and the sub-shell of the calandria by inserting a cutting device into the inner part of the calandria vault through the upper part of the calandria vault; and drawing out the main shell of the calandria to the outside of the calandria vault by moving the support device from the inner part of the calandria vault to the outside through the upper part.
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公开(公告)号:US11830632B2
公开(公告)日:2023-11-28
申请号:US17278462
申请日:2019-09-20
发明人: Young Hwan Hwang , Seok-Ju Hwang , Ju-Young Yoon , Cheon-Woo Kim
摘要: A device for separating a shielding slab for a heavy water reactor according to an embodiment includes: a body; a circular rail installed on at least one side of the body; and a decommissioner for decommissioning a shielding slab installed on the circular rail and installed on an inner wall of a heavy water reactor, wherein the decommissioner includes a decommission head moving on the circular rail, a separator installed in the decommission head and separating and desalinizing the shielding slab, and a gripper installed in the decommission head and gripping the separated shielding slab.
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公开(公告)号:US20230298774A1
公开(公告)日:2023-09-21
申请号:US18019129
申请日:2021-08-03
发明人: Eun-ki LEE
IPC分类号: G21C17/104
CPC分类号: G21C17/104
摘要: A method of dynamic control rod reactivity measurement for a reactor using a fission chamber as an out-of-reactor measuring instrument includes: maintaining the reactor in a critical state having a set output by inserting a reference control bank into a reactor core to a first depth; completely inserting the reference control bank into the reactor core from the first depth at a maximum allowable speed and immediately completely withdrawing the reference control bank from the reactor core at the maximum allowable speed, and measuring a first signal of the out-of-reactor measuring instrument from before the insertion of the reference control bank to after the withdrawal of the reference control bank; and determining static controllability of the reference control bank by adding residual controllability measurement value of the reactor to a first static reactivity of the reactor calculated using the first signal of the out-of-reactor measuring instrument.
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