scholarly journals Investigation of interaction between heat transfer and cladding swelling in light water reactor LOCA analysis. Final report

1979 ◽  
Author(s):  
D. S. Rowe
Keyword(s):  
Heat Transfer ◽  
Light Water Reactor ◽  
Final Report ◽  
Light Water ◽  
Water Reactor

scholarly journals Multi-Applications Small Light Water Reactor - NERI Final Report

2003 ◽  
Author(s):  
S. Michale Modro ◽  
James E. Fisher ◽  
Kevan D. Weaver ◽  
Jr. Jose N. Reyes ◽  
John T. Groome ◽  
...  
Keyword(s):  
Light Water Reactor ◽  
Final Report ◽  
Light Water ◽  
Water Reactor

scholarly journals RETRAN sensitivity studies of light water reactor transients. Final report

1977 ◽  
Author(s):  
N. S. Burrell ◽  
G. C. Gose ◽  
J. F. Harrison ◽  
G. R. Sawtelle
Keyword(s):  
Light Water Reactor ◽  
Final Report ◽  
Light Water ◽  
Water Reactor ◽  
Sensitivity Studies

scholarly journals A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation

Energies ◽  
2020 ◽  
Vol 13 (23) ◽  
pp. 6374
Author(s):  
Alexey Cherezov ◽  
Jinsu Park ◽  
Hanjoo Kim ◽  
Jiwon Choe ◽  
Deokjung Lee
Keyword(s):  
Heat Transfer ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Time Step ◽  
Light Water ◽  
Water Reactor ◽  
Adaptive Time Step ◽  
Accident Simulation ◽  
Adaptive Time ◽  
Coupling Algorithm

A new reactor core multi-physics system addresses the pellet-to-cladding heat transfer modeling to improve full-core operational transient and accident simulation used for assessment of reactor core nuclear safety. The rigorous modeling of the heat transfer phenomena involves strong interaction between neutron kinetics, thermal-hydraulics and nuclear fuel performance, as well as consideration of the pellet-to-cladding mechanical contact leading to dramatic increase in the gap thermal conductance coefficient. In contrast to core depletion where parameters smoothly depend on fuel burn-up, the core transient is driven by stiff equation associated with rapid variation in the solution and vulnerable to numerical instability for large time step sizes. Therefore, the coupling algorithm dedicated for multi-physics transient must implement adaptive time step and restart capability to achieve prescribed tolerance and to maintain stability of numerical simulation. This requirement is met in the MPCORE (Multi-Physics Core) multi-physics system employing external loose coupling approach to facilitate the coupling procedure due to little modification of constituent modules and due to high transparency of coupling interfaces. The paper investigates the coupling algorithm performance and evaluates the pellet-to-cladding heat transfer effect for the rod ejection accident of a light water reactor core benchmark.

scholarly journals Multi-Application Small Light Water Reactor Final Report

2003 ◽  
Author(s):  
S.M. Modro ◽  
J.E. Fisher ◽  
K.D. Weaver ◽  
J.N. Reyes ◽  
J.T. Groome ◽  
...  
Keyword(s):  
Light Water Reactor ◽  
Final Report ◽  
Light Water ◽  
Water Reactor
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