Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor

2020 ◽  
Vol 149 ◽  
pp. 107747
Author(s):  
Qiyue Lu ◽  
Rizwan-uddin
Keyword(s):  
Stability Analysis ◽  
Fast Reactor ◽  
Natural Circulation ◽  
Thermal Hydraulics

Nuclear-Coupled Thermal Hydraulics Stability of a Natural Circulation Lead-Cooled Fast Reactor

2014 ◽  
Author(s):  
Qiyue Lu ◽  
Rizwan Uddin
Keyword(s):  
Fast Reactor ◽  
Natural Circulation ◽  
Expansion Method ◽  
Design Stage ◽  
Thermal Hydraulics ◽  
Coupled Models ◽  
Feedback Effects ◽  
Modal Expansion ◽  
Reduced Order ◽  
Modal Expansion Method

Stability analyses are carried out for a natural circulation lead-cooled fast reactor which is at its design stage. Because of its natural circulation feature, flow stability as well as nuclear-coupled thermal hydraulics stability is of some concern. Modal Expansion Method (MEM) and Reduced Order Model (ROM) are used for neutronics and thermal hydraulics part, respectively. These two separate models are coupled through feedback effects. Different simulation scenarios on the separate and coupled models are reported.

Natural circulation capability of Pb-Bi cooled fast reactor: PEACER

2000 ◽  
Vol 37 (1-4) ◽  
pp. 211-216 ◽  
Author(s):  
Jong-Eun Chang ◽  
Kune Y. Suh ◽  
Il Soon Hwang
Keyword(s):  
Fast Reactor ◽  
Natural Circulation

scholarly journals MELT-III: a neutronics, thermal-hydraulics computer program for fast reactor safety analysis. Volume II

1974 ◽  
Author(s):  
A.E. Waltar ◽  
W.L. Partain ◽  
D.C. Kolesar ◽  
L.D. O'Dell ◽  
A. Jr. Padilla ◽  
...  
Keyword(s):  
Computer Program ◽  
Fast Reactor ◽  
Safety Analysis ◽  
Thermal Hydraulics ◽  
Reactor Safety
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