Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Ji-Han Chun"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 554-564 (2022)
The natural circulation phenomena occurring in fully integrated nuclear reactors are associated with a unique formation mechanism. The phenomenon results from a structural feature of these reactors involving upward flow from the core, located in the
Externí odkaz:
https://doaj.org/article/771fc92118694aa4880e7dfe156efe9f
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 554-564 (2022)
The natural circulation phenomena occurring in fully integrated nuclear reactors are associated with a unique formation mechanism. The phenomenon results from a structural feature of these reactors involving upward flow from the core, located in the
Publikováno v:
Progress in Nuclear Energy. 85:617-623
SMART is a small sized integral type pressurized water reactor and its design minimizes the potential for an occurrence of transients and accidents. To achieve these purposes, engineered safety features enhance the accident resistance. A large volume
Publikováno v:
Nuclear Engineering and Design. 289:287-295
The FCM fueled cores proposed as an accident tolerant concept is assessed against the design-basis-accident (DBA) and the beyond-DBA (BDBA) scenarios using MARS code. A thermal conductivity model of FCM fuel is incorporated in the MARS code to take i
Autor:
Ji-Han Chun, Kyoo-Hwan Bae, Bub-Dong Chung, Keung-Koo Kim, Guy-Hyung Lee, Young-Jong Chung, Young In Kim
Publikováno v:
Nuclear Engineering and Design. 277:138-145
A safety evaluation of SMART adopting a fully passive safety system was performed for a small-break loss of coolant accident (SBLOCA) with various break locations and sizes using the MARS code. It is necessary for SMART, adopting a fully passive safe
Publikováno v:
Nuclear Engineering and Design. 254:291-299
TASS/SMR-S is thermal-hydraulic design code for safety analysis of SMART plant. SBLOCA is considered as the design basis accident in the SMART. The capability of TASS/SMR-S for SBLOCA analysis was assessed using LOFT L3-7 as TMI action plan. Because
Publikováno v:
Annals of Nuclear Energy. 37:730-739
The purpose of this study is to develop a severe accident (SA) analysis method that is more reliable thorough transferring the physical status of the plant predicted by RELAP5 computer code to MAAP4 computer code. The methodology of the linkage analy
Publikováno v:
Annals of Nuclear Energy. 37:471-481
In order to identify and quantify the key parameters affecting the predictions of fission product transport and plate-out behavior in the coolant circuits of a very high temperature reactor (VHTR) system, systematic and intensive analyses were perfor
Autor:
Goon-Cherl Park, Ji-Han Chun
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers B. 33:643-657
Publikováno v:
Nuclear Engineering and Technology. 41:691-708
In order to analyze thermal hydraulic phenomena during a DVI (Direct Vessel Injection) line break LOCA (Loss-of-Coolant Accident) in the APR1400 (Advanced Power Reactor 1400 MWe), we performed experimental studies with the SNUF (Seoul National Univer