Zobrazeno 1 - 10
of 16
pro vyhledávání: '"InHyung Kim"'
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
Improved deterministic truncation of the Monte Carlo (iDTMC) solution method has been applied to neutronic depletion analyses of a nuclear reactor in this work. The theoretical background on the iDTMC method and material depletion calculation is brie
Externí odkaz:
https://doaj.org/article/8b739ed15c7e4cd1acc4b613d07ddf05
Autor:
Yu-Jin Hong, Inhyung Kim
Publikováno v:
Korean Society for the Sociology of Sport. 36:1-20
Autor:
Inhyung Kim
Publikováno v:
The Korean Journal of Physical Education. 61:31-43
Publikováno v:
Sports Science. 39:361-368
Autor:
Won-Woo Park, Inhyung Kim
Publikováno v:
The Korean Journal of Physical Education. 60:31-43
Autor:
InHyung Kim, JeeHyun Kim
Publikováno v:
Journal of Korean Society of Sport Policy. 17:21-35
Publikováno v:
Nuclear Science and Engineering. 194:14-31
This paper presents a systematic way to truncate the high-fidelity Monte Carlo (MC) solution to reduce the computational cost without compromising the essential reliability of the solution....
Autor:
Inhyung Kim, Yonghee Kim
Publikováno v:
EPJ Web of Conferences, Vol 247, p 04023 (2021)
This paper presents the application and evaluation of a deterministic truncation of Monte Carlo (DTMC) solution method in a whole core reactor problem based on a continuous energy transport calculation. The DTMC method has been studied and developed
Autor:
Yonghee Kim, Inhyung Kim
Publikováno v:
Annals of Nuclear Energy. 166:108723
An improved deterministic truncation of Monte Carlo (iDTMC) solution method has been developed for acceleration and variance reduction of Monte Carlo (MC) neutronic analysis. A new calculational strategy has been applied by taking advantages of parti
Publikováno v:
Annals of Nuclear Energy. 95:86-101
This paper presents the neutronics conceptual design of a long-life 392.6 MWth innovative sodium-cooled fast reactor (iSFR). The iSFR, which was derived based on Korean Prototype Generation-IV sodium cooled fast reactor (PGSFR), was intended as an al