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Kim, Woong Ki; Kim, Ji Hyun
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2020
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2020
AbstractAbstract
[en] Ministry of Science and ICT (MSIT) and National Research Council of Science and Technology (NST) of government designed a manpower development project to train the unemployed young generations in the field of the 4th industrial revolution based on the researchers and research infrastructure of government-funded research institutes in 2018. The research institutes participated in the project to train the trainees for the practical technologies required to have a job in the medium and small-sized companies. Nuclear Training and Education Center (KNTC) of Korea Atomic Energy Research Institute (KAERI) participated in the project based on the survey results of the employment plans of KAERI family companies. KNTC operated 7 training programs for 13 young trainees about nuclear safety including nuclear safety assessment, analysis of thermal hydraulics, radiation sensor, production of medical isotopes using laser, UV laser, electron accelerator, radiation biology utilizing researchers and research infrastructures of KAERI during 12 months from April in 2019 to March in 2020. The trainees studied the theory and practical technologies through the programs, 10 trainees had a job in some nuclear companies after finishing the programs. The trainees will be helpful for the innovation and growth of the companies
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Apr 2020; 77 p; Also available from KAERI; 16 figs, 52 tabs; This record replaces 53092217
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Kim, Ji Hyun
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2019
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2019
AbstractAbstract
[en] Ministry of Science and ICT(MSIT) and National Research Council of Science and Technology(NST) of government designed a manpower development project to train the unemployed young generations in the field of the 4th industrial revolution based on the researchers and research infrastructure of government-funded research institutes in 2018. The research institutes participated in the project to train the trainees for the practical technologies required to have a job in the medium and small-sized enterprises. Nuclear Training and Education Center(KNTC) of Korea Atomic Energy Research Institute(KAERI) participated in the project based on the survey results of the employment plans of KAERI family companies. KNTC operated a training program about nuclear safety for 2 young people utilizing researchers and research infrastructures of KAERI during 6 months from August in 2018 to February in 2019. The trainees studied the theory and practical technologies for the probabilistic safety assessment of nuclear facilities through this program, A trainee had a job in the KAERI family company after finishing the program. The trainee will be helpful for the innovation and growth of the company
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Apr 2019; 54 p; Also available from KAERI; 1 ref, 6 figs, 23 tabs
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Report
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Nam, Young Mi; Hwang, Hye Seon
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2018
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2018
AbstractAbstract
[en] For the education and training of nuclear industry personnel, some education and training programs based on KAERI’s advanced technologies were implemented. The professional education programs have been developed and implemented for the employees in the nuclear field related to radiation treatment technologies, probabilistic safety assessment, decommissioning of nuclear facilities, and reactor core design. For the development of next generation human resources, the project has developed the specialized education programs for the students of undergraduate course and of graduate course from nuclear engineering departments, making the most use of experimental equipment and providing practical exercise with the research facilities which are particularly available at KAERI. Courses for technical expertise have been developed and offered for building capacity of the nuclear R&D staff members. Nuclear basic courses with field trip have been implemented for residents, the government employees, middle school students and teachers for the public acceptance and understanding on nuclear activities and related safety. Some lecture rooms and a rest lounge in the NTC building have been upgraded to improve the education environment. As the final outcome, the project has developed 6 new education programs as well as 20 new education materials, and also offered 30 courses to 3,382 people including 1,409 industry employees, 57 university students, 758 local residents, and 1,158 KAERI R&D staff members. The project offered the internship program to train 126 university students, 38 people started graduate course and doctoral course in cooperation with universities in 2018
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Dec 2018; 254 p; Also available from KAERI; 8 refs, 47 figs, 130 tabs
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Report
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INIS IssueINIS Issue
Kim, Woong Ki; Kim, S. S.; Lee, J. W. and others
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
AbstractAbstract
[en] DUPIC fuel manufacturing technologies and processes have been developed at DFDF(DUPIC Fuel Development Facility, IMEF M6). Using DUPIC powder prepared by the oxidation and reduction processes, the DUPIC fuel pellets and mini-elements were fabricated for the irradiation test and performance evaluation at HANARO. In this study, the irradiation test was planned for the performance evaluation of DUPIC fuel pellets and elements at NRU. To establish fabrication process satisfying the requirements of NRU irradiation test, sintered DUPIC pellets were fabricated with a variety of process parameters involving compaction pressure and characterized by the inspection system. As a result of the experiment, DUPIC pellets with 12.19 mm of diameter, 10.37∼10.45 g/cm3 of sintered density, and less than Ra 0.8μm of surface roughness have been successfully fabricated at hot cell. The optimum DUPIC pellet fabrication process satisfying the requirements of NRU irradiation has been established based on the result of this experiment
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Feb 2002; 38 p; 7 refs, 8 figs, 15 tabs
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CHEMICAL REACTIONS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FABRICATION, FUELS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS, MATERIALS TESTING REACTORS, NATURAL URANIUM REACTORS, NUCLEAR FUELS, PELLETS, POOL TYPE REACTORS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, TESTING, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Kim, S. S.; Lee, J. W.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
AbstractAbstract
[en] In this study, 10 DUPIC pellets and two mini-elements were fabricated to investigate the thermal characteristics of DUPIC fuel in December 2003. As a result of the experiment, DUPIC pellets with 10.310∼10.415 g/cm3 (95.3∼96.3 % of T.D.) of sintered density and less than Ra 0.76 μm of surface roughness satisfying the specifications of DUPIC fuel for the 5th irradiation test have been remotely fabricated at hot cell. 5 DUPIC pellets including 3 pellets equipped with thermal sensor in the center of the pellet were loaded in a mini-element. Endcap welding of the mini-element was performed by Nd:YAG laser. The soundness of the weld of the mini-element has been confirmed by microstructural test, helium leak test, and X-ray inspection. The DUPIC mini-elements assembled in an instrumented rig are under the irradiation at HANARO reactor
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Mar 2004; 32 p; Available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 8 refs, 6 figs, 10 tabs
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Report
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ENRICHED URANIUM REACTORS, FABRICATION, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, JOINING, MATERIALS TESTING REACTORS, PELLETS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, TESTING, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Kim, S. S.; Lee, J. W.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
AbstractAbstract
[en] The irradiation test of DUPIC fuel at NRU was planned for the evaluation of DUPIC fuel performance. To establish fabrication process satisfying the requirements of NRU irradiation test, sintered DUPIC pellets were fabricated, and the pellets were characterized by the inspection systems. The optimum process parameters for DUPIC pellet fabrication have been established based on the pre-qualification test for the irradiation testing at NRU. In this study, the qualification test was performed to qualify the fabrication processes developed by the pre-qualification test. As a result of the test, DUPIC pellets with 12.189∼12.200 mm of diameter, 10.31∼10.43 g/cm3 of sintered density, and less than Ra 0.8μm of surface roughness have been successfully fabricated at hot cell. Based on the result of the test, the DUPIC pellet fabrication processes were qualified for NRU irradiation test
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May 2002; 29 p; 8 refs, 5 figs, 13 tabs
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Report
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CHEMICAL REACTIONS, EQUIPMENT, FABRICATION, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LABORATORY EQUIPMENT, NATURAL URANIUM REACTORS, PELLETS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Nam, Y. M.; Hwang, H. S.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2017
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2017
AbstractAbstract
[en] For the education and training of nuclear industry personnel, some education and training programs based on KAERI’s advanced technologies were implemented. The professional education programs have been developed and implemented for the employees in the nuclear field related to radiation treatment technologies, probabilistic safety assessment, nuclear safety technology, nuclear power plant simulator, and reactor core design. For the development of next generation human resources, the project has developed the specialized education programs for the students from nuclear engineering departments and from radiology and radiopharmacy in universities, making the most use of experimental equipment and providing practical exercise with the research facilities which are particularly available at KAERI. Courses for technical expertise have been developed and offered for building capacity of the nuclear R&D staff members. Nuclear basic courses with field trip have been implemented for residents, the government employees, middle school students and teachers for the public acceptance and understanding on nuclear activities and related safety. Some lecture rooms and a rest lounge in the NTC building have been upgraded to improve the education environment. As the final outcome, the project has developed 4 new education programs as well as 16 new education materials, and also offered 32 courses to 3,196 people including 1,475 industry employees, 161 university students, 369 local residents, and 1,191 KAERI R&D staff members. The project offered the internship program to train 140 university students, 27 people started graduate course and doctoral course in cooperation with universities in 2017
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Dec 2017; 262 p; Also available from KAERI; 7 refs, 41 figs, 133 tabs
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Shin, Jin Myeong; Shin, Byung Chul
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2020
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2020
AbstractAbstract
[en] For the education and training of nuclear industry personnel, some education and training programs based on KAERI’s advanced technologies were implemented. The professional education programs have been developed and implemented for the employees in the nuclear field related to radiation treatment technologies, analysis of radioactivity, and nuclear analysis technology. For the development of next generation human resources, the project has developed the specialized education programs for the students of undergraduate course and of graduate course from nuclear engineering departments, making the most use of experimental equipment and providing practical exercise with the research facilities which are particularly available at KAERI. Courses for technical expertise have been developed and offered for building capacity of the nuclear R&D staff members. Nuclear basic courses with field trip have been implemented for residents, the government employees, and teachers for the public acceptance and understanding on nuclear activities and related safety. Some lecture rooms in the NTC building have been upgraded to improve the education environment. As the final outcome, the project has developed 2 new education programs as well as 18 new education materials, and also offered 26 courses to 2,048people including 848 industry employees, 116 university students, 79 local residents, and 1,005 KAERI R&D staff members. The project offered the internship program to train 58 university students, 18 people started graduate course and doctoral course in cooperation with universities in 2020
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Dec 2020; 240 p; Also available from KAERI; 9 refs, 48 figs, 130 tabs; This record replaces 53092241
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Report
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Experiment on the improvement of OREOX process for fabrication of dry recycling nuclear fuel pellets
Kim, Woong Ki; Kim, S. S.; Park, G. I.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
AbstractAbstract
[en] The OREOX(Oxidation and REduction of OXide fuel) process has been performed to fabricate dry recycling(DUPIC ; Direct Use of spent PWR fuel In CANDU reactor) nuclear fuel pellets by using spent PWR fuel. Generally, sinterable DUPIC powder has been manufactured from spent PWR fuel pellets by the 3 cycles of oxidation and reduction treatment. The OREOX process is one of the most important processes for DUPIC pellet fabrication. A lot of time more than 37 hours as well as a lot of reaction gas is required to perform 3 cycles of OREOX treatments. In this experiment, 1 cycle OREOX process was adopted to improve the powdering process of DUPIC pellet manufacturing processes. As a result of experiment, the densities of pellets sintered at 1800 .deg. C for 10 hours ranged from 10.15 to 10.22 g/cm3(93.8∼94.5 % of T.D.). The pellets were sintered again to increase the sintered density. The sintered densities of pellets re-sintered at 1850 .deg. C for 7 hours ranged from 10.27 to 10.33 g/cm3(94.9∼ 95.5 % of T.D)
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Jan 2004; 30 p; Available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 5 refs, 17 figs, 11 tabs
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Kim, S. S.; Lee, J. W.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
AbstractAbstract
[en] In this study, based on the simulated DUPIC fuel fabrication experiment and DUPIC fuel characterization experiment at PIEF, DUPIC fuel manufacturing technologies and processes have been developed at DFDF(DUPIC Fuel Development Facility, IMEF M6). Using DUPIC powder prepared by the oxidation and reduction processes, the DUPIC fuel pellets were fabricated and characterized in terms of the process parameters such as the burn-up of spent fuel, compaction pressure, sintering temperature, and sintering time. As a result of the experiment, DUPIC pellets were characterized by 10.02 ∼ 10.43 g/cm3 of sintered density, 7.26 ∼ 9.48μm of grain size, and less than Ra 0.8μm of surface roughness at hot cell. The optimum DUPIC processes have been established based on the results of the experiment
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Jan 2002; 55 p; 5 refs, 25 figs, 23 tabs
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