Results 51 to 60 of about 128 (71)
, 2017 Downward discharge behavior and porosity analysis were conducted in this paper. In the HCDA of the metal fueled SFR, fuel melts. The molten fuel is ejected into the coolant channel by accumulated pressure inside of the cladding owing to fission gas. Some
Bang, In Cheol +3 more
core
Aseismic Performance Evaluation Of a PGSFR PHTS Pump
, 2019 Lee Jaehan, Kim Sungkyun, Lee Seonghyeon
core
Optimization of Design Variables of ALIP for the Circulation of Sodium Coolant in the PGSFR
, 2016 Kim, Hee Reyoung, Kwak, JaeSik
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Computation of Thermal Striping in the Upper Plenum of PGSFR
Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, 2014 A computational study of a thermal striping in the upper plenum of the PGSFR (Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at KAERI (Korea Atomic Energy Research Institute) is presented. First, previous experimental and numerical studies on the thermal striping are briefly discussed.
Seok-Ki Choi, Choi Seok-Ki
exaly +3 more sources
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 +4 more sources
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.
Seung-Hwan Seong
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 +2 more
exaly +3 more sources