PRELIMINARY ANALYSIS OF SODIUM EXPERIMENTAL APPARATUS PLANDTL-2 FOR DEVELOPMENT OF EVALUATION METHOD FOR THERMAL HYDRAULICS IN REACTOR VESSEL OF SODIUM FAST REACTOR UNDER DECAY HEAT REMOVAL SYSTEM OPERATION CONDITION

2019 ◽  
Vol 2019.27 (0) ◽  
pp. 2318
Author(s):  
Ayako ONO ◽  
Masaaki TANAKA ◽  
Yasuhiro MIYAKE ◽  
Erina HAMASE ◽  
Toshiki Ezure
Keyword(s):  
Evaluation Method ◽  
Heat Removal ◽  
Reactor Vessel ◽  
System Operation ◽  
Operation Condition ◽  
Decay Heat ◽  
Sodium Fast Reactor ◽  
Experimental Apparatus ◽  
Heat Removal System ◽  
Removal System

Pre-design of an innovative passive decay heat removal system for ATRIUM AMR-SFR

2021 ◽  
Vol 378 ◽  
pp. 111259
Author(s):  
A. Pantano ◽  
P. Gauthe ◽  
M. Errigo ◽  
P. Sciora
Keyword(s):  
Heat Removal ◽  
Decay Heat ◽  
Heat Removal System ◽  
Removal System

scholarly journals BWR decay heat removal system appraisal

1978 ◽  
Author(s):  
J. E. Kelly ◽  
R. C. Erdmann
Keyword(s):  
Heat Removal ◽  
Decay Heat ◽  
Heat Removal System ◽  
Removal System

S-CO2 Turbine Design for Decay Heat Removal System of Sodium Cooled Fast Reactor

2016 ◽  
Author(s):  
Seong Kuk Cho ◽  
Jekyoung Lee ◽  
Jeong Ik Lee ◽  
Jae Eun Cha
Keyword(s):  
Experimental Data ◽  
Fast Reactor ◽  
Design Methodology ◽  
Nuclear Reactors ◽  
Heat Removal ◽  
Design Code ◽  
Decay Heat ◽  
Turbine Design ◽  
Heat Removal System ◽  
Removal System

A Sodium-cooled Fast Reactor (SFR) has receiving attention as one of the promising next generation nuclear reactors because it can recycle the spent nuclear fuel produced from the current commercial nuclear reactors and accomplish higher thermal efficiency than the current commercial nuclear reactors. However, after shutdown of the nuclear reactor core, the accumulated fission products of the SFR also decay and release heat via radiation within the reactor. To remove this residual heat, a decay heat removal system (DHRS) with supercritical CO2 (S-CO2) as the working fluid is suggested with a turbocharger system which achieves passive operational capability. However, for designing this system an improved S-CO2 turbine design methodology should be suggested because the existing methodology for designing the S-CO2 Brayton cycle has focused only on the compressor design near the critical point. To develop a S-CO2 turbine design methodology, the non-dimensional number based design and the 1D mean line design method were modified and suggested. The design methodology was implemented into the developed code and the code results were compared with existing turbine experimental data. The data were collected under air and S-CO2 environment. The developed code in this research showed a reasonable agreement with the experimental data. Finally using the design code, the turbocharger design for the suggested DHRS and prediction of the off design performance were carried out. As further works, more effort will be put it to expand the S-CO2 turbine test data for validating the design code and methodology.

scholarly journals Analysis on inadvertent operation of decay heat removal system in NuScale reactor

2019 ◽  
Author(s):  
Susyadi ◽  
Andi S. Ekariansyah ◽  
Hendro Tjahjono ◽  
D. T. Sony Tjahyani
Keyword(s):  
Heat Removal ◽  
Decay Heat ◽  
Heat Removal System ◽  
Removal System

Thermal-hydraulic analysis of an innovative decay heat removal system for lead-cooled fast reactors

2016 ◽  
Vol 305 ◽  
pp. 168-178 ◽  
Author(s):  
Fabio Giannetti ◽  
Damiano Vitale Di Maio ◽  
Antonio Naviglio ◽  
Gianfranco Caruso
Keyword(s):  
Heat Removal ◽  
Hydraulic Analysis ◽  
Fast Reactors ◽  
Decay Heat ◽  
Heat Removal System ◽  
Thermal Hydraulic Analysis ◽  
Removal System
Sign in / Sign up

Export Citation Format

Share Document