Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Chungho Cho"'
Publikováno v:
Nuclear Technology. 169:134-142
As part of the development of a safety analysis methodology for a liquid-metal reactor (LMR) in Korea, the Multidimensional Analysis of Reactor Safety (MARS) code was selected as a system transient safety analysis code. The Korea Atomic Energy Resear
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9950957629a8ca05fef806310bdb6d02
https://doi.org/10.13182/nt10-a9358
https://doi.org/10.13182/nt10-a9358
Autor:
Kwi-Seok Ha, Young-Min Kwon, Yong-Bum Lee, Hae-Yong Jeong, Dohee Hahn, Soo-Dong Suk, Won-Pyo Chang, Chungho Cho
Publikováno v:
Nuclear Engineering and Technology. 41:1053-1064
The existence of a large sodium pool in the KALIMER, a pool-type LMR developed by the Korea Atomic Energy Research Institute, plays an important role in reactor safety and operability because it determines the grace time for operators to cope with an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f9ce6718925bd7391307d584583f670a
https://doi.org/10.5516/net.2009.41.8.1053
https://doi.org/10.5516/net.2009.41.8.1053
Publikováno v:
Nuclear Engineering and Technology. 41:797-806
The Multichannel Analyzer for Transient and steady-state in Rod Array - Liquid Metal Reactor for Flow Blockage analysis (MATRA-LMR-FB) code for the analysis of a subchannel blockage has been developed and evaluated through several experiments. The cu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c6803b46ace560baec5b29f14ce722f
https://doi.org/10.5516/net.2009.41.6.797
https://doi.org/10.5516/net.2009.41.6.797
Publikováno v:
Annals of Nuclear Energy. 35:1256-1263
KAERI (Korea Atomic Energy Research Institute) is developing an accelerator driven system (ADS) named HYPER (HYbrid Power Extraction Reactor) for a transmutation of long-lived nuclear wastes. One of the challenging tasks for the HYPER system is to de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3db4bce0e77fd0e9a52549fdddfcc701
https://doi.org/10.1016/j.anucene.2007.12.011
https://doi.org/10.1016/j.anucene.2007.12.011
Publikováno v:
Nuclear Engineering and Design. 238:90-101
A spallation target system is a key component to be developed for an accelerator driven system (ADS). It is known that a 15–25 MW spallation target is required for a practical 1000 MWth ADS. The design of a 20 MW spallation target is very challengi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::784af87083ad024e2e4f9145a4a2452b
https://doi.org/10.1016/j.nucengdes.2007.06.011
https://doi.org/10.1016/j.nucengdes.2007.06.011
Publikováno v:
Journal of Nuclear Science and Technology. 44:294-302
For a prismatic VHTR fuel assembly, a physics study has been performed to maximize the fuel performance in terms of the cycle length and the discharge burnup for a given fuel enrichment. The relationship between the fuel performance and the fuel conf
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1bf172fa59ba63080656300e4db1b696
https://doi.org/10.1080/18811248.2007.9711285
https://doi.org/10.1080/18811248.2007.9711285
Publikováno v:
Volume 3: Thermal Hydraulics; Instrumentation and Controls.
The Korea Atomic Energy Research Institute (KAERI) is developing a Generation IV sodium-cooled fast reactor design equipped with a passive decay heat removal circuit (PDRC), which is a unique safety system in the design. The performance of the PDRC s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::19e1afea38cacede1ad06439bd07cb65
https://doi.org/10.1115/icone16-48639
https://doi.org/10.1115/icone16-48639
Publikováno v:
Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management.
KAERI (Korea Atomic Energy Research Institute) is developing an accelerator-driven transmutation system called HYPER (HYbrid Power Extraction Reactor). HYPER is the 1000 MW{sub th} system designed to transmute the long-lived TRU (Transuranic Elements
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8cb5bcfc4e9659166a8c08b8845577a5
https://doi.org/10.1115/icone14-89600
https://doi.org/10.1115/icone14-89600
Publikováno v:
Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.
KAERI (Korea Atomic Energy Research Institute) is developing an accelerator driven system (ADS) named HYPER (HYbrid Power Extraction Reactor) for a transmutation of long-lived nuclear wastes. One of the challenging tasks for the HYPER system is to de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae196b173c8d9e0a71178561a20124e7
https://doi.org/10.1115/icone14-89400
https://doi.org/10.1115/icone14-89400
Publikováno v:
Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum.
Lead corrosion test loop named KPAL-II (KAERI Pb Alloy Loop II) has been designed and fabricated at the Korea Atomic Energy Research Institute (KAERI) and an initial operation was performed recently. The KPAL-II was designed to study the long-term co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11d3c4775bcfeb828882e0ed7e8dccb9
https://doi.org/10.1115/icone14-89376
https://doi.org/10.1115/icone14-89376