Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Tung Dong Cao Nguyen"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4048-4056 (2023)
The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper. The performance of the MCS/RAST-F code system is assessed usin
Externí odkaz:
https://doaj.org/article/a58a131debe4484689a6a2fac7c70404
Autor:
Nhan Nguyen Trong Mai, Kyeongwon Kim, Matthieu Lemaire, Tung Dong Cao Nguyen, Woonghee Lee, Deokjung Lee
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 7, Pp 2670-2689 (2022)
STREAM - a lattice transport calculation code with method of characteristics for the purpose of light water reactor analysis - has been developed by the Computational Reactor Physics and Experiment laboratory (CORE) of the Ulsan National Institute of
Externí odkaz:
https://doaj.org/article/7a010c3eabf14cc79f29858a6a9ec7be
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2788-2802 (2021)
Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported. The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified
Externí odkaz:
https://doaj.org/article/01ae5c232bbd426e8678f9474789e566
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 5, Pp 878-888 (2020)
This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity simulation of commercial pressurized water reactors (PWRs). Its focus is on the accurate, spatially detailed neutronic analyses of startup physics te
Externí odkaz:
https://doaj.org/article/0a99882c532e467e9e93fbb10f12642a
Autor:
Eun Jeong, Jiwon Choe, Muhammad Farid Khandaq, Tung Dong Cao Nguyen, Deokjung Lee, Douglas A. Fynan
Publikováno v:
International Journal of Energy Research. 45:12426-12448
Autor:
Tung Dong Cao Nguyen, Deokjung Lee
Publikováno v:
Computer Physics Communications. 285:108642
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 5, Pp 878-888 (2020)
This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity simulation of commercial pressurized water reactors (PWRs). Its focus is on the accurate, spatially detailed neutronic analyses of startup physics te
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02007 (2021)
Recent researches have become more interested in the feasibility of using Monte Carlo (MC) code to generate multi-group (MG) cross sections (XSs) for fast reactor analysis using nodal diffusion codes. The current study, therefore, presents a brief me
Publikováno v:
International Journal of Energy Research. 43:254-273
Autor:
Ho Cheol Shin, Vutheam Dos, Hanjoo Kim, Seongpil Yum, Wonkyeong Kim, Woonghee Lee, Masao Yamanaka, Cheol Ho Pyeon, Jaerim Jang, Tung Dong Cao Nguyen, Jiwon Choe, Khang Hoang Nhat Nguyen, Deokjung Lee, Chidong Kong
Publikováno v:
Annals of Nuclear Energy. 118:92-98
This study presents the first application of the advanced Rossi-alpha method (theoretically introduced by Kong et al., 2014) on the reactivity measurements in a research reactor: detector count signals at the Kyoto University Critical Assembly (KUCA)