Thermal-Hydraulic Analysis for HEU and LEU Transitional Core Conversion of the MIT Research Reactor

2013 ◽  
Vol 182 (3) ◽  
pp. 315-334 ◽  
Author(s):  
Sung Joong Kim ◽  
Lin-Wen Hu ◽  
Floyd Dunn
Keyword(s):  
Research Reactor ◽  
Hydraulic Analysis ◽  
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

Transient Thermal-Hydraulic Analysis of Single Flow Channel Blockage in the JRR-3M 20-MW Research Reactor

2018 ◽  
Vol 204 (1) ◽  
pp. 15-24 ◽  
Author(s):  
Yuchuan Guo ◽  
Guanbo Wang ◽  
Dazhi Qian ◽  
Heng Yu ◽  
Bo Hu ◽  
...  
Keyword(s):  
Research Reactor ◽  
Flow Channel ◽  
Hydraulic Analysis ◽  
Channel Blockage ◽  
Transient Thermal ◽  
Single Flow ◽  
Thermal Hydraulic Analysis

scholarly journals TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

2017 ◽  
Vol 8 (4) ◽  
pp. 698 ◽  
Author(s):  
Anhar Riza Antariksawan ◽  
Efrizon Umar ◽  
Surip Widodo ◽  
Mulya Juarsa ◽  
Mukhsinun Hadi Kusuma
Keyword(s):  
Research Reactor ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis

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.

Neutronic and thermal–hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core

2016 ◽  
Vol 116 ◽  
pp. 178-184 ◽  
Author(s):  
E. Chham ◽  
T. El Bardouni ◽  
K. Benaalilou ◽  
H. Boukhal ◽  
B. El Bakkari ◽  
...  
Keyword(s):  
Research Reactor ◽  
Reactor Core ◽  
Hydraulic Analysis ◽  
Triga Mark Ii ◽  
Thermal Hydraulic Analysis

Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1

2008 ◽  
Vol 35 (2) ◽  
pp. 345-352 ◽  
Author(s):  
A. Mushtaq ◽  
Massod Iqbal ◽  
Ishtiaq Hussain Bokhari ◽  
Tariq Mahmood ◽  
Tayyab Mahmood ◽  
...  
Keyword(s):  
Research Reactor ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis
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