Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Taewoo Tak"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 1, Pp 25-36 (2023)
Nuclear power plants have recognized the importance of nuclear cybersecurity. Based on regulatory guidelines and security-related standards issued by regulatory agencies around the world including IAEA, NRC, and KINAC, nuclear operating organizations
Externí odkaz:
https://doaj.org/article/7271a81f6ad44141b4881f23c95ae1de
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 1, Pp 6-16 (2017)
This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code. The reactivity changes when the coolant was voided were a
Externí odkaz:
https://doaj.org/article/887e5836f3f24e248459bbd9eced807f
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 6, Pp 1360-1367 (2016)
This paper introduces a boron meter with improved accuracy compared with other commercially available boron meters. Its design includes a new fitting function and a multi-detector. In pressurized water reactors (PWRs) in Korea, many boron meters have
Externí odkaz:
https://doaj.org/article/1b1a905a0c3d46269b98562c756b7099
Publikováno v:
Journal of Nuclear Science and Technology. 54:705-715
This paper presents consistent and rigorous accuracy assessments of various methods for calculating the diffusion coefficients in a two-step reactor core analysis of light water reactors (LWRs). The diffusion coefficients are significantly affected b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::73299c273a20d29e29ee3b6a46366585
https://doi.org/10.1080/00223131.2017.1299648
https://doi.org/10.1080/00223131.2017.1299648
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 1, Pp 6-16 (2017)
This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code. The reactivity changes when the coolant was voided were a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ccd74e104a5dc36b14eb77b53bd9868b
http://www.sciencedirect.com/science/article/pii/S1738573316301048
http://www.sciencedirect.com/science/article/pii/S1738573316301048
Publikováno v:
Thorium—Energy for the Future ISBN: 9789811326578
A design study of ultra-long cycle fast reactor with a rated power of 1000 MWe (UCFR-1000) was performed to flatten its radial power distribution throughout the cycle depletion of the core. It is expected that the flattening of the radial power distr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e86c270ae5c6a96bf350868eb02aa9cf
https://doi.org/10.1007/978-981-13-2658-5_30
https://doi.org/10.1007/978-981-13-2658-5_30
Publikováno v:
International Journal of Energy Research. 41:139-148
Summary This paper presents a new design for a small modular sodium-cooled fast reactor core with an optimized lifetime and reactivity swing through the analysis of various breed-and-burn strategies and its neutronic analyses in terms of active core
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e53621753185e938773d5a06642b6a20
https://doi.org/10.1002/er.3609
https://doi.org/10.1002/er.3609
Publikováno v:
International Journal of Energy Research. 40:1662-1672
Summary This paper presents a design study of power shape flattening for an optimized ultra-long cycle fast reactor with a power rate of 1000 MWe in order to mitigate the power peaking issue and improve the safety with a lower maximum neutron flux an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7da38b2a6b2d71e98c162740f5ef9ca3
https://doi.org/10.1002/er.3552
https://doi.org/10.1002/er.3552
Publikováno v:
International Journal of Energy Research. 39:1859-1878
This paper reviews the feasibility of ultralong-cycle operation on a compact liquid metal-cooled fast reactor (LMR) firstly by assessing the operation of a long-life fast reactor core and secondly by evaluating material performance in respect to both
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::65bfb2b5ec013184f12eca9097fe1540
https://doi.org/10.1002/er.3384
https://doi.org/10.1002/er.3384
Publikováno v:
AIP Conference Proceedings.
To develop an advanced long-life SMR core concept, the feasibility of the long-life breed-and-burn core concept has been assessed and the preliminary selection on the reactor design requirement such as fuel form, coolant material has been performed.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b007bdf8fdfaf6102df0a38b2a204472
https://doi.org/10.1063/1.4940059
https://doi.org/10.1063/1.4940059