Patents by Inventor Geun-Il Park
Geun-Il Park has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).
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Patent number: 11810684Abstract: The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.Type: GrantFiled: August 24, 2021Date of Patent: November 7, 2023Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTEInventors: Ki Rak Lee, Hwan Seo Park, Geun Il Park, Hong Joo Ahn, Jung Hoon Choi, Hyun Woo Kang, In Tae Kim
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Publication number: 20220068517Abstract: The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.Type: ApplicationFiled: August 24, 2021Publication date: March 3, 2022Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTEInventors: Ki Rak LEE, Hwan Seo PARK, Geun Il PARK, Hong Joo AHN, Jung Hoon CHOI, Hyun Woo KANG, In Tae KIM
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Publication number: 20180185813Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.Type: ApplicationFiled: January 3, 2018Publication date: July 5, 2018Inventors: Jae Hwan Yang, Jin-Myeong Shin, Jang Jin Park, Geun-Il Park
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Patent number: 9889425Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.Type: GrantFiled: December 23, 2014Date of Patent: February 13, 2018Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTEInventors: Jae Hwan Yang, Jin-Myeong Shin, Jang Jin Park, Geun-Il Park
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Patent number: 9711247Abstract: A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated.Type: GrantFiled: December 29, 2014Date of Patent: July 18, 2017Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTEInventors: Young-Hwan Kim, Jae-Won Lee, Geun-il Park, In-Tae Kim
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Patent number: 9368242Abstract: There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.Type: GrantFiled: December 27, 2013Date of Patent: June 14, 2016Assignee: Korea Atomic Energy Research InstituteInventors: Hee-Chul Eun, Yung-Zun Cho, Jung Hoon Choi, Hwan Seo Park, Hee-Chul Yang, JunHong Kim, Tae-Kyo Lee, Geun-il Park
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Publication number: 20160042821Abstract: A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated.Type: ApplicationFiled: December 29, 2014Publication date: February 11, 2016Inventors: Young-Hwan Kim, Jae-Won Lee, Geun-il Park, In-Tae KIM
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Patent number: 8969646Abstract: A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.Type: GrantFiled: September 5, 2013Date of Patent: March 3, 2015Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.Inventors: Jin-Myeong Shin, Jae Hwan Yang, Jang Jin Park, Youngja Kim, Geun-Il Park
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Publication number: 20140374653Abstract: There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.Type: ApplicationFiled: December 27, 2013Publication date: December 25, 2014Applicant: Korea Atomic Energy Research InstituteInventors: Hee-Chul EUN, Yung-Zun CHO, Jung Hoon CHOI, Hwan Seo PARK, Hee-Chul YANG, JunHong KIM, Tae-Kyo LEE, Geun-il PARK
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Patent number: 8802013Abstract: A vol-oxidizer for spent nuclear fuel is provided. The vol-oxidizer includes a reactor module in which the spent nuclear fuel is put and oxidized; a heating module to heat the reactor module to a high temperature; a utility module to control an inner state of the reactor module, being connected with the reactor module; a support module to support the heating module and the reactor module; a drive module to supply a driving force for transferring the spent nuclear fuel within the reactor module; a valve module to control discharge of the spent nuclear fuel being oxidized in the reactor module; and a collecting container module to collect the spent nuclear fuel being oxidized and discharged from the reactor module. The respective modules are assembled and disassembled with respect to one another.Type: GrantFiled: May 11, 2011Date of Patent: August 12, 2014Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.Inventors: Young Hwan Kim, Geun Il Park, Jae Hoo Jung, Jung Won Lee, Ki Ho Kim, Young Soon Lee, Do Youn Lee
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Publication number: 20140114112Abstract: A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.Type: ApplicationFiled: September 5, 2013Publication date: April 24, 2014Applicants: Korea Hydro & Nuclear Power Co., Ltd., Korea Atomic Energy Research InstituteInventors: Jin-Myeong SHIN, Jae Hwan YANG, Jang Jin PARK, Youngja KIM, Geun-Il PARK
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Publication number: 20130289329Abstract: The present disclosure relates to a decontamination method and apparatus for cladding hull wastes of spent nuclear fuels, capable of decontaminating a small quantity of spent nuclear fuels remaining on surfaces of the cladding hull wastes and radioactive fission products penetrated into the cladding hulls through an electrochemical dissolution. The method includes inserting the cladding hull waste into an anodic basket, immersing a reference electrode and a cathodic electrode as well as the anodic basket in a molten salt, dissolving a surface of the cladding hull waste by applying a voltage or current to the anodic basket with respect to the cathodic electrode or the reference electrode, removing the anodic basket, and removing a salt remaining on the surface of the cladding hull waste.Type: ApplicationFiled: October 17, 2012Publication date: October 31, 2013Applicant: Korea Atomic Energy Research InstituteInventors: Chang Hwa LEE, Min Ku JEON, Kweon Ho KANG, Geun Il Park
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Patent number: 8535636Abstract: Disclosed herein is a method of separating group II nuclides from a radioactive waste lithium chloride salt and recovering renewable lithium chloride, comprising the steps of: injecting lithium oxide into a lithium chloride salt containing group II nuclides to convert the group II nuclides into thermally-stable oxide or oxychloride; and vaporizing and condensing the lithium chloride salt under a reduced pressure condition to separate the group II nuclides and recover recyclable lithium chloride. The method is advantageous in that group II nuclides existing in the form of chloride, which is not highly thermally-stable in a lithium chloride (LiCl) to salt and is not easily solidified, can be converted into oxides or oxychlorides, which is highly thermally-stable in the lithium chloride (LiCl) salt and is easily solidified, without producing impurities.Type: GrantFiled: September 21, 2012Date of Patent: September 17, 2013Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.Inventors: Hee Chul Eun, Yung Zun Cho, Hwan Seo Park, Tae Kyo Lee, In Tae Kim, Geun Il Park
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Publication number: 20120051978Abstract: A vol-oxidizer for spent nuclear fuel is provided. The vol-oxidizer includes a reactor module in which the spent nuclear fuel is put and oxidized; a heating module to heat the reactor module to a high temperature; a utility module to control an inner state of the reactor module, being connected with the reactor module; a support module to support the heating module and the reactor module; a drive module to supply a driving force for transferring the spent nuclear fuel within the reactor module; a valve module to control discharge of the spent nuclear fuel being oxidized in the reactor module; and a collecting container module to collect the spent nuclear fuel being oxidized and discharged from the reactor module. The respective modules are assembled and disassembled with respect to one another.Type: ApplicationFiled: May 11, 2011Publication date: March 1, 2012Inventors: Young Hwan Kim, Geun Il Park, Jae Hoo Jung, Jung Won Lee, Ki Ho Kim, Young Soon Lee, Do Youn Lee
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Patent number: 5719093Abstract: A method and an apparatus are disclosed for desorbing TEDA by utilizing a fluidized bed so as to reuse a used impregnated active carbon for the purpose of removing toxic materials from a fluid. The impregnated active carbon is injected into a fluidized bed at a high temperature to carry out a desorbing process, in such a manner that TEDA and CH.sub.3 l are desorbed from the impregnated active carbon at a high temperature by utilizing the high volatility of TEDA and CH.sub.3 l. If a heated air is injected through an air inlet into the desorbing tower, the high temperature air and the used impregnated active carbon are met in a fluidized state, with the result that the active carbon with TEDA and CH.sub.3 l desorbed is discharged.Type: GrantFiled: December 14, 1995Date of Patent: February 17, 1998Assignee: Korea Atomic Energy ResearchInventors: Geun-Il Park, Myeong-Soo Jeong, Bum-Hoe Kim, Hoo-Kun Lee