Results 71 to 80 of about 171 (84)

Design optimization analysis of a large electromagnetic pump for sodium coolant transportation in PGSFR

Annals of Nuclear Energy, 2018
Abstract An annular linear induction electromagnetic pump (ALIP) with a flow rate of 0.86 m 3 /s and a developed pressure of 3.6 bar is designed by conducting an optimization analysis of its geometrical, electromagnetic, and hydrodynamic variables. The purpose of the ALIP involves circulating liquid sodium in the intermediate heat transport system of
Jaesik Kwak, Hee Reyoung Kim
exaly   +3 more sources

The sensitivity analysis for IHTS and SG due to the Large-scale Sodium-Water Reaction event in PGSFR

Annals of Nuclear Energy, 2018
Abstract The Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR) is being developed by Korea Atomic Energy Research Institute (KAERI). As a reactor coolant, it uses sodium to transfer the core heat energy to the turbine. Sodium has a chemical characteristics that it violently reacts with materials such as water and air. The Steam Generator (SG)
Chiwoong Choi, Taekyeong Jeong, Seung Won Lee   +2 more
exaly   +2 more sources

Design and validation of a fuel assembly simulator for PGSFR reactor flow distribution test facility

Nuclear Engineering and Design, 2020
Abstract A test facility to investigate the flow characteristics inside reactor vessel for the Prototype Gen-IV Sodium-cooled Fast Reactor was constructed. In the test facility, reactor vessel and the main in-vessel components are linearly reduced at a scaling ratio of 1/5 and water is used as the working fluid.
Woo Shik Kim, Seung Hyun Hong, Hae Seob Choi, Sun Rock Choi, Dong Jin Euh   +4 more
openaire   +1 more source

System design strategies of Post-Accident Monitoring System for a PGSFR in KOREA

2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), 2013
Monitoring systems of a PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor) in KOREA provide alarms, integrity information in the reactor building, sodium-water reaction information in the steam generator, fuel failure information, and supporting information for maintenance and inspection.
null Gwi-sook Jang, null Kwang-il Jeong, null Jong-yong Keum, null Seung-hwan Seong   +3 more
openaire   +1 more source

Large eddy simulation of thermal striping in the upper plenum of the PGSFR

Journal of Nuclear Science and Technology, 2015
Seok-Ki Choi, Sungho Ko
exaly  

Thermal-hydraulic analyses of passive reactor vault cooling system (RVCS) in PGSFR using MARS-LMR

Annals of Nuclear Energy, 2018
Chiwoong Choi, Taekyeong Jeong
exaly  

ICONE23-1331 RANS BASED CFD METHODOLOGY AND CHALLENGE IN MODELING REAL SCALE 217-PIN WIRE-WRAPPED FUEL ASSEMBLY OF KAERI PGSFR

The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2015
Jae-Ho Jeong, Jin Yoo, Kwi-Lim Lee, Kwi-Seok Ha, Hae-Yong Jeong   +4 more
openaire   +1 more source

Assessment of ex-core neutron detectors in prototype Gen-IV sodium-cooled fast reactor (PGSFR)

Annals of Nuclear Energy, 2019
Donny Hartanto
exaly  

Analyses of UTOP events for the design of control rod stop system in PGSFR using MARS-LMR

Annals of Nuclear Energy, 2016
Chiwoong Choi
exaly  

RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR

Nuclear Engineering and Design, 2017
Jae-Ho Jeong, Song Minseop
exaly