Burn-up effect on inherent safety parameters and reactivity insertion transient analysis of Pakistan Research Reactor-1

2012 ◽  
Vol 58 ◽  
pp. 1-5 ◽  
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood
Keyword(s):  
Transient Analysis ◽  
Research Reactor ◽  
Inherent Safety ◽  
Safety Parameters ◽  
Reactivity Insertion

Transient analysis of Ghana Research Reactor-1 using PARET/ANL thermal–hydraulic code

2009 ◽  
Vol 239 (11) ◽  
pp. 2479-2483 ◽  
Author(s):  
E. Ampomah-Amoako ◽  
E.H.K. Akaho ◽  
S. Anim-Sampong ◽  
B.J.B. Nyarko
Keyword(s):  
Transient Analysis ◽  
Research Reactor

scholarly journals Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor

2018 ◽  
Vol 50 (7) ◽  
pp. 1017-1023 ◽  
Author(s):  
Mina Torabi ◽  
A. Lashkari ◽  
Seyed Farhad Masoudi ◽  
Somayeh Bagheri
Keyword(s):  
Research Reactor ◽  
Control Rod ◽  
Tehran Research Reactor ◽  
Safety Parameters

scholarly journals OPTIMIZATION OF FUEL RELOADING PATTERNS FOR A RESEARCH REACTOR BY SIMULATED ANNEALING

2011 ◽  
Vol 14 (1) ◽  
pp. 63-71
Author(s):  
Binh Quang Do
Keyword(s):  
Simulated Annealing ◽  
Optimization Problem ◽  
Research Reactor ◽  
Diffusion Theory ◽  
Computer Code ◽  
Decision Variable ◽  
Safety Parameters ◽  
Fortran Language ◽  
Dalat Research Reactor ◽  
Effective Multiplication

This article presents results obtained from a research into an application of simulated annealing method to the in-core fuel reloading pattern optimization for a research reactor. The decision variable of the optimization problem is a fuel reloading pattern for the next cycle after the present cycle finishes. The objective function maximizes the effective multiplication factor keff at the beginning of cycle while it is established to include an important safety paramater – the power peaking factor, in search process. A procedure for searching the optimal solutions was formed and a computer code was developed in the Fortran language running on PCs. Nuclear safety parameters for the optimization problem are provided from the results of the multigroup neutron diffusion theory computation program CITATION. A sample calculation was performed to find the optimal fuel reloading patterns for the second cycle of the Dalat research reactor and the results are presented in this article.

Evaluation of neutronic safety parameters of the BAEC TRIGA Research Reactor with Wet Central Tube

2019 ◽  
Vol 124 ◽  
pp. 533-540
Author(s):  
Md. Saifur Rahman ◽  
M.A. Malek Soner ◽  
M. Mizanur Rahman ◽  
Md. Al Amin Hossain ◽  
M.A. Salam ◽  
...  
Keyword(s):  
Research Reactor ◽  
Central Tube ◽  
Safety Parameters

Transient analysis of break below the grid in Tehran research reactor using the newly enhanced COBRA-EN code

2012 ◽  
Vol 49 ◽  
pp. 1-11 ◽  
Author(s):  
M. Aghaie ◽  
A. Zolfaghari ◽  
A. Minuchehr ◽  
A. Shirani ◽  
A. Norouzi
Keyword(s):  
Transient Analysis ◽  
Research Reactor ◽  
Tehran Research Reactor

scholarly journals Reactivity insertion transient analysis for KUR low-enriched uranium silicide fuel core

2013 ◽  
Vol 62 ◽  
pp. 195-207 ◽  
Author(s):  
Xiuzhong Shen ◽  
Ken Nakajima ◽  
Hironobu Unesaki ◽  
Kaichiro Mishima
Keyword(s):  
Transient Analysis ◽  
Enriched Uranium ◽  
Reactivity Insertion ◽  
Uranium Silicide
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