Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Nam-Il Tak"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 9, Pp 1974-1982 (2020)
Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR). The results are used for the maintenance and repair of the
Externí odkaz:
https://doaj.org/article/cb0ec8bfafbb477783430ac31f90218e
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02041 (2021)
Recently, the coupling between computer codes that simulate different physical phenomena has attracted for more accurate analysis. In the case of high-temperature gas-cooled reactor (HTGR), the coupling between neutronics and thermal-fluid analysis i
Externí odkaz:
https://doaj.org/article/192cc6753344490eb8fcca2a2cd8ca11
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 641-654 (2014)
A new computer code, named CORONA (Core Reliable Optimization and thermo-fluid Network Analysis), was developed for the core thermo-fluid analysis of a prismatic gas cooled reactor. The CORONA code is targeted for whole-core thermo-fluid analysis of
Externí odkaz:
https://doaj.org/article/d348460159794e3fb316221e5d01005f
Autor:
NAM-IL TAK, MIN-HWAN KIM, HONG-SIK LIM, JAE MAN NOH, TIMOTHY J. DRZEWIECKI, VOLKAN SEKER, THOMAS J. DOWNAR, JOSEPH KELLY
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 6, Pp 745-752 (2013)
For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of M
Externí odkaz:
https://doaj.org/article/4b174d0b4a7f48249f738edd1bd220e7
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 9, Pp 1974-1982 (2020)
Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR). The results are used for the maintenance and repair of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::36458c93f16fcee5b501716f44e81eed
https://doi.org/10.1016/j.net.2020.02.006
https://doi.org/10.1016/j.net.2020.02.006
Autor:
Nam-Il Tak, Sung Nam Lee
Publikováno v:
Fusion Science and Technology. 76:238-245
The High-Temperature Gas-cooled Reactor (HTGR) has been selected as one of the next-generation nuclear power plants because of its passive safety features. The Korea Atomic Energy Research Institut...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dc7fdf5af1c378a15003c8559b8609b1
https://doi.org/10.1080/15361055.2019.1705725
https://doi.org/10.1080/15361055.2019.1705725
Publikováno v:
Nuclear Engineering and Design. 399:112002
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fb7cd73e2e3d711e12363be53cba1112
https://doi.org/10.1016/j.nucengdes.2022.112002
https://doi.org/10.1016/j.nucengdes.2022.112002
Publikováno v:
Nuclear Engineering and Design. 340:156-165
The High Temperature Gas-Cooled Reactor (HTGR), as a Gen-IV reactor, adopts a Reactor Cavity Cooling System (RCCS) to remove core decay heat after a reactor trip. During a postulated accident such as a pipe break in the reactor coolant system, the co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2e7faf37474be7d5eedbd0c966f824c8
https://doi.org/10.1016/j.nucengdes.2018.09.029
https://doi.org/10.1016/j.nucengdes.2018.09.029
Publikováno v:
Journal of Nuclear Science and Technology. 54:668-680
This paper presents the application results of MCS/GAMMA+ to multi-physics analysis of OECD/NEA modular high temperature gas-cooled reactor (MHTGR) benchmark Phase I Exercise 3. It is a part of int...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a4a784741faa4020ffa6ea87395eb8bb
https://doi.org/10.1080/00223131.2017.1299649
https://doi.org/10.1080/00223131.2017.1299649
Publikováno v:
EPJ Web of Conferences; 2021, Vol. 247, p1-8, 8p