scholarly journals Development and validation of new algorithms for control rods insertion modeling in the RAPID code system using the JSI TRIGA Mark-II reactor

2022 ◽  
Vol 166 ◽  
pp. 108711
Author(s):  
Valerio Mascolino ◽  
Alireza Haghighat ◽  
Luka Snoj
Keyword(s):  
Code System ◽  
Triga Mark Ii ◽  
Development And Validation ◽  
Control Rods ◽  
New Algorithms

Development and validation of burnup-transport code system OMCB for accelerator driven system

2017 ◽  
Vol 324 ◽  
pp. 360-371 ◽  
Author(s):  
Jin-Yang Li ◽  
Long Gu ◽  
Rui Yu ◽  
Nadezda Korepanova ◽  
Hu-Shan Xu
Keyword(s):  
Code System ◽  
Transport Code ◽  
Driven System ◽  
Accelerator Driven System ◽  
Development And Validation

Estimation of control rod worth, xenon effect on reactivity and power defect of BAEC TRIGA Mark-II research reactor

2018 ◽  
Vol 33 (39) ◽  
pp. 1850233
Author(s):  
Md. Mehedi Hassan ◽  
K. M. Jalal Uddin Rumi ◽  
Md. Nazrul Islam Khan ◽  
Rajib Goswami
Keyword(s):  
Theoretical Analysis ◽  
Low Power ◽  
Temperature Effects ◽  
Research Reactor ◽  
Power Level ◽  
Fuel Temperature ◽  
Control Rod ◽  
Full Power ◽  
Triga Mark Ii ◽  
Control Rods

In this work, control rod worth, xenon (Xe) effect on reactivity and power defect have been measured by doing experiments in the BAEC TRIGA Mark-II research reactor (BTRR) and through established theoretical analysis. Firstly, to study the xenon-135 effect on reactivity, reactor is critical at 2.4 MW for several hours. Next, experiments have been performed at very low power (50 W) to avoid temperature effects. Moreover, for the power defect experiment, different increasing power level has been tested by withdrawing the control rods. Finally, it is concluded that the total control rods worth of the BAEC TRIGA Mark-II research reactor, as determined through this study, is enough to run the reactor at full power (3 MW) considering the xenon-135 and fuel temperature effects.

Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors

2014 ◽  
Author(s):  
Tengfei Zhang ◽  
Hongchun Wu ◽  
Youqi Zheng ◽  
Liangzhi Cao ◽  
Yunzhao Li
Keyword(s):  
Least Square Method ◽  
Least Square ◽  
Core Analysis ◽  
Code System ◽  
Lattice Calculation ◽  
Control Rod ◽  
Research Reactors ◽  
The Core ◽  
User Friendly ◽  
Control Rods

As an effort to enhance the accuracy in simulating the operations of research reactors, a fuel management code system REFT was developed. Because of the possible complex assembly geometry and the core configuration of research reactors, the code system employed HELIOS in the lattice calculation to describe arbitrary 2D geometry, and used the 3D triangular nodal SN method transport solver, DNTR, to model unstructured geometry in the core analysis. Flux reconstruction with the least square method and micro depletion model for specific isotopes were incorporated in the code. At the same time, to make it more user friendly, a graphical user interface was also developed for REFT. In the analysis of the research reactors, the calculations involving the control rod movement are encountered frequently. The modeling of the control rods differential worth behavior is important in that the movement of the control rod may introduce variations on the reactivity. To handle the problem two effective ways of alleviating the control rod cusping effect are recently proposed, based on the established code system. The methodologies along with their application and validation will be discussed.

Neutronics analysis of the 3MW TRIGA Mark-II research reactor by using SRAC code system

2008 ◽  
Vol 35 (6) ◽  
pp. 1140-1146 ◽  
Author(s):  
M.M. Sarker ◽  
S.I. Bhuiyan ◽  
M.M. Akramuzzaman
Keyword(s):  
Research Reactor ◽  
Code System ◽  
Triga Mark Ii

Development and validation of the new coupled code system TRADYN

2018 ◽  
Vol 112 ◽  
pp. 685-692 ◽  
Author(s):  
Jose Angel Gonzalez-Vargas ◽  
V.H. Sanchez-Espinoza ◽  
R. Stieglitz ◽  
R. Macian-Juan
Keyword(s):  
Code System ◽  
Development And Validation

Development and Validation of SACATRI Code for Thermal-Hydraulic Analysis of the CENM TRIGA MARK II

2009 ◽  
Author(s):  
Ossama Merroun ◽  
Ahmed Al Mers ◽  
Marcelo A. Veloso ◽  
Tarek El Bardouni
Keyword(s):  
Research Reactor ◽  
Channel Model ◽  
Power Level ◽  
Reactor Core ◽  
Start Up ◽  
Triga Mark Ii ◽  
Physics Modeling ◽  
Reactor Operating ◽  
Development And Validation ◽  
Thermal Hydraulic Analysis

The Moroccan TRIGA MARK II research reactor operating at power level of 2MW under natural convection regime was acquired by the CENM-Morocco in the aim of developing nuclear technology and its application in the industry and scientific research. Since 2007, start up tests have been performed on this reactor to verify that thermal, mechanical and neutronic parameters fall within the ranges allowing the safe and reliable working conditions of the reactor core. For these purposes, a thermal-hydraulic code named SACATRI, based on sub-channel model, was developed to satisfy the need of numerical simulation tool, able to predict the different thermal-hydraulic parameters of the coolant flow. In the aim of corroborating the physics modeling of the code, the present study is devoted to the quantification of the model accuracy obtained by comparing responses from SACATRI computational model with experimentally measured responses realized on the IPR-R1 TRIGA research reactor.

scholarly journals On Line Measurement of Reactivity Worth of TRIGA Mark-II Research Reactor Control Rods

2011 ◽  
Vol 02 (09) ◽  
pp. 1024-1029 ◽  
Author(s):  
Nusrat Jahan ◽  
Mamunur M. Rashid ◽  
F. Ahmed ◽  
M. G. S. Islam ◽  
M. Aliuzzaman ◽  
...  
Keyword(s):  
Research Reactor ◽  
Reactor Control ◽  
Line Measurement ◽  
On Line ◽  
Triga Mark Ii ◽  
Control Rods
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