Results 1 to 10 of about 70 (57)

A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

Nuclear Engineering and Technology, 2016
AbstractKorea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and ...
Kwi Lim Lee, Kwi-Seok Ha, Jae-Ho Jeong, Chi-Woong Choi, Taekyeong Jeong, Sang June Ahn, Seung Won Lee, Won-Pyo Chang, Seok Hun Kang, Jaewoon Yoo   +9 more
doaj   +11 more sources

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Nuclear Engineering and Technology, 2016
AbstractThe 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 transuranic elements included in light water reactor spent nuclear fuel.
Jaewoon Yoo, Jinwook Chang, Jae-Yong Lim, Jin-Sik Cheon, Tae-Ho Lee, Sung Kyun Kim, Kwi Lim Lee, Hyung-Kook Joo   +7 more
doaj   +5 more sources

Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector

Nuclear Engineering and Technology, 2016
AbstractThe Korean Prototype Gen-IV sodium-cooled fast reactor (PGSFR) is supposed to be loaded with a relatively-costly low-enriched U fuel, while its envisaged transuranic fuels are not available for transmutation. In this work, the U-enrichment reduction by improving the neutron economy is pursued to save the fuel cost.
Chihyung Kim, Donny Hartanto, Yonghee Kim   +2 more
doaj   +5 more sources

Drop Performance Test of Control Rod Assembly for Prototype Gen-IV Sodium-cooled Fast Reactor

Transactions of the Korean Society of Pressure Vessels and Piping, 2016
Young Kyu Lee, Hoe Woong Kim, Jae Han Lee, Gyeong Hoi Koo, Jong Bum Kim, Sung Kyun Kim   +5 more
openaire   +4 more sources

Conceptual designs and characteristic of the fuel handling and transfer system for 150 MWe PGSFR and 1400 MWe SFR burner reactor

Nuclear Engineering and Technology, 2022
KAERI (Korea Atomic Energy Research Institute) developed the conceptual design of PGSFR (Prototype Gen-IV Sodium Cooled Fast Reactor) and Burner Reactor. Since the reactor characteristics of the PGSFR and Burner Reactor are different, the shape, size and
Kang-Soo Kim, Jong-Bum Kim, Chang-Gyu Park   +2 more
doaj   +1 more source

Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor

Nuclear Technology, 2019
AbstractThe SAS4A safety analysis code, originally developed for the analysis of postulated severe accidents in oxide fuel sodium-cooled fast reactors (SFRs), has been significantly extended to all...
A. M. Tentner, A. Karahan, S. H. Kang
openaire   +2 more sources

A validation study of the SLTHEN code for hexagonal assemblies of wire-wrapped pins using liquid metal heating experiments

Nuclear Engineering and Technology
This paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR).
Sun Rock Choi, Junkyu Han, Huee-Youl Ye, Jonggan Hong, Won Sik Yang   +4 more
doaj   +1 more source

Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]

Heliyon, 2023
Agbevanu KT, Debrah SK, Arthur EM, Shitsi E.   +3 more
europepmc   +1 more source

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review. [PDF]

Materials (Basel), 2022
Alba R, Iglesias R, Cerdeira MÁ.
europepmc   +1 more source

Spin Hyperpolarization in Modern Magnetic Resonance. [PDF]

Chem Rev, 2023
Eills J, Budker D, Cavagnero S, Chekmenev EY, Elliott SJ, Jannin S, Lesage A, Matysik J, Meersmann T, Prisner T, Reimer JA, Yang H, Koptyug IV.   +12 more
europepmc   +1 more source