Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D

2009 ◽  
Vol 162 (3) ◽  
pp. 261-274 ◽  
Author(s):  
W. R. Marcum ◽  
B. G. Woods ◽  
M. R. Hartman ◽  
S. R. Reese ◽  
T. S. Palmer ◽  
...  
Keyword(s):  
Steady State ◽  
State University ◽  
Hydraulic Analysis ◽  
Triga Reactor ◽  
Oregon State University ◽  
Thermal Hydraulic Analysis

Thermal-Hydraulic Analysis of the 3-MW TRIGA MARK-II Research Reactor under Steady-State and Transient Conditions

2001 ◽  
Vol 135 (1) ◽  
pp. 51-66 ◽  
Author(s):  
M. Q. Huda ◽  
S. I. Bhuiyan ◽  
T. K. Chakrobortty ◽  
M. M. Sarker ◽  
M. A. W. Mondal
Keyword(s):  
Steady State ◽  
Research Reactor ◽  
Hydraulic Analysis ◽  
Transient Conditions ◽  
Triga Mark Ii ◽  
Thermal Hydraulic Analysis

A Comparison of Pulsing Characteristics of the Oregon State University TRIGA Reactor with FLIP and LEU Fuel

2012 ◽  
Vol 171 (2) ◽  
pp. 150-164 ◽  
Author(s):  
W. R. Marcum ◽  
T. S. Palmer ◽  
B. G. Woods ◽  
S. T. Keller ◽  
S. R. Reese ◽  
...  
Keyword(s):  
State University ◽  
Triga Reactor ◽  
Oregon State University

scholarly journals Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1

2011 ◽  
Vol 26 (1) ◽  
pp. 45-49 ◽  
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood
Keyword(s):  
Steady State ◽  
Research Reactor ◽  
Safety Margin ◽  
Nucleate Boiling ◽  
Hydraulic Analysis ◽  
The Core ◽  
Computer Codes ◽  
Neutronic Parameters ◽  
Thermal Hydraulic Analysis

The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4. Reactor codes WIMS/D4 and CITATION have been used for the calculations of neutronic parameters including peaking factors and power profiles at different burn-up considering a xenon free core and also the equilibrium xenon values. RELAP5/MOD3.4 code was utilized for the determination of peak fuel centerline, clad and coolant temperatures to ensure the safety of the reactor throughout the cycle. The calculations reveal that the reactor is safe and no nucleate boiling will commence at any part of the core throughout the cycle and that the safety margin increases with burnup as peaking factors decrease.

Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRs

2009 ◽  
Vol 239 (8) ◽  
pp. 1544-1559 ◽  
Author(s):  
P. Ferroni ◽  
C.S. Handwerk ◽  
N.E. Todreas
Keyword(s):  
Steady State ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis
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