[HTML][HTML] Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea
J Yoo, J Chang, JY Lim, JS Cheon, TH Lee… - Nuclear Engineering …, 2016 - Elsevier
Abstract The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for
the last 4 years, fulfilling the technology demonstration of the burning capability of …
the last 4 years, fulfilling the technology demonstration of the burning capability of …
[PDF][PDF] Evaluation on In-vessel Source Term in PGSFR (2017 Results)
SW Lee, W Chang, K Ha, SJ Ahn, SH Kang… - Transactions of the …, 2016 - kns.org
The potential for accidents to cause the release of radionuclides into the public environment
is the source of safety concern with the use of nuclear reactors for power generation …
is the source of safety concern with the use of nuclear reactors for power generation …