scholarly journals Initial Criticality Analysis of Malaysia’s TRIGA Research Reactor Using TRIGLAV Computer Code

2018 ◽  
Vol 7 (4.35) ◽  
pp. 899
Author(s):  
M. A Khattak ◽  
Abdoulhdi A. Borhana ◽  
Nurul Syahrizzat M. Yasin ◽  
Rustam Khan ◽  
Juniza Md Saad
Keyword(s):  
Diffusion Equation ◽  
Power Distribution ◽  
Research Reactor ◽  
Nuclear Research ◽  
Computer Code ◽  
Experimental Result ◽  
Zirconium Hydride ◽  
Finite Differences Method ◽  
Triga Mark Ii ◽  
Criticality Analysis

Malaysian Nuclear Agency hosts the 1MW Thermal TRIGA MARK II research reactor since 1982. It first initial criticality was achieved on 28th June 1982 with loading of solid fuel elements like Uranium Zirconium Hydride. TRIGA MARK II started its operation of the research reactor on the same year with a 1MW power generation. Training, Research, Isotope Production and General Atomic (TRIGA) is designed to successfully actualize the variety fields of fundamental nuclear research, the manpower training and the production of radioisotopes. This study deals with the initial criticality analysis of the TRIGA research reactor using TRIGLAV reactor physics computer program. For this purpose, a model of its initial core will be developed and simulated using the software and the results will be validated against the experimental result as mentioned in the final safety analysis report (FSAR). The TRIGLAV computer code solves the neutron diffusion equation by using a finite differences method with iteration of fission density. TRIGLAV is based on four group time independent diffusion equation in two dimensional cylindrical (r, θ) geometry.  TRIGLAV can also be applied for criticality of reactor, fuel burn-up calculations, and power distribution and flux distributions calculations of the core and also the reactivity predictions of the reactor.  

Evaluation of Rubidium and Potassium Diffusion in Soil by Radiotracer Technique

2014 ◽  
Vol 353 ◽  
pp. 199-204 ◽  
Author(s):  
E. Demir ◽  
A.B. Tugrul ◽  
N. Baydogan ◽  
A.F. Baytaş ◽  
N. Altinsoy ◽  
...  
Keyword(s):  
Scintillation Detector ◽  
Research Reactor ◽  
Nuclear Research ◽  
Potassium Nitrate ◽  
Soil Columns ◽  
Radiotracer Technique ◽  
The Earth ◽  
Nuclear Research Reactor ◽  
Triga Mark Ii ◽  
Radioactivity Measurements

In this study, diffusion of rubidium and potassium in soil was observed representing two alkaline elements. Generally, these elements are found as salt compounds in the earth. Soil columns were prepared in the laboratory conditions. Rubidium chlorite and potassium nitrate compounds were irradiated at ITU TRIGA Mark II nuclear research reactor at the Energy Institute of ITU to produce the radiotracer 86Rb and 42K. The irradiated compounds were sprinkled to the surface of different soil columns and were watered with realistic amounts. Radioactivity measurements were carried out by using a scintillation detector at the outside of the column for different soil depths in different diffusion times. As the results of the study, the behavior of two alkaline elements was observed appropriately similar in the soil.

scholarly journals Calculation Results for Enhancing Ability of I-131 Radioisotope Production Using Tellurium Dioxide Target on the Dalat Nuclear Research Reactor

2021 ◽  
Vol 9 (3) ◽  
Author(s):  
Cuong Nguyen Kien ◽  
Nghiem Huynh Ton ◽  
Vinh Le Vinh ◽  
Vien Luong Ba ◽  
Huy Pham Quang ◽  
...  
Keyword(s):  
Research Reactor ◽  
Nuclear Research ◽  
Computer Code ◽  
Total Activity ◽  
Radioisotope Production ◽  
Original Design ◽  
Operational Conditions ◽  
Safety Requirements ◽  
Nuclear Research Reactor ◽  
Calculation Results

The paper presents the calculation results in re-design of neutron trap of the Dalat Nuclear Research Reactor (DNRR) for I-131 radioisotope production using TeO2 target. The new design permits for loading more TeO2 capsules from 9 to 12, 15 and 18 in the neutron trap. The enhancement of radioisotope production was implemented by re-arrangement of the neutron trap without changing the dimension or geometry of irradiation capsules. By using neutronics computer code as MCNP6, the obtained calculation results of I-131 activity in 6 investigated cases showed that the new design by the re-arrangement of the neutron trap can be used effectively for radioisotope production with thermal neutron flux in average range from 5.3×1012 to 1×1013 n/cm2.s and the total activity of I-131 isotope was increased from about 19.2% to 38.8% comparing with the original design using 9 capsules. The negative reactivity insertion was from 0.60 βeff to 0.96 βeff when loading capsules that also met the safety requirements of operational conditions of the DNRR.

scholarly journals Design Analyses for Full Core Conversion of The Dalat Nuclear Research Reactor

2014 ◽  
Vol 4 (1) ◽  
pp. 10-25
Author(s):  
Ba Vien Luong ◽  
Vinh Vinh Le ◽  
Ton Nghiem Huynh ◽  
Kien Cuong Nguyen
Keyword(s):  
Steady State ◽  
Power Distribution ◽  
Research Reactor ◽  
Nuclear Research ◽  
Coolant Temperature ◽  
Thermal Hydraulics ◽  
Kinetics Parameters ◽  
Nuclear Research Reactor ◽  
Enriched Uranium ◽  
Full Core

The paper presents calculated results of neutronics, steady state thermal hydraulics and transient/accidents analyses for full core conversion from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU) of the Dalat Nuclear Research Reactor (DNRR). In this work, the characteristics of working core using 92 LEU fuel assemblies and 12 beryllium rods were investigated by using many computer codes including MCNP, REBUS, VARI3D for neutronics, PLTEMP3.8 for steady state thermal hydraulics, RELAP/MOD3.2 for transient analyses and ORIGEN, MACCS2 for maximum  hypothetical accident (MHA). Moreover, in neutronics calculation, neutron flux, power distribution, peaking factor, burn up distribution, feedback reactivity coefficients and kinetics parameters of the working core were calculated. In addition, cladding temperature, coolant temperature and ONB margin were estimated in steady state thermal hydraulics investigation. The working core was also analyzed under initiating events of uncontrolled withdrawal of a control rod, cooling pump failure, earthquake and MHA. Obtained results show that DNRR loaded with LEU fuel has all safety features as HEU and mixed HEU-LEU fuel cores and meets requirements in utilization as well.

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