Analyses of THAI 1 hydrogen deflagration using MELCOR code version 2.1 and 2.2

2020 ◽  
Vol 369 ◽  
pp. 110838
Author(s):  
A. Flores y Flores ◽  
G. Mazzini
Keyword(s):  
Code Version

Comparison of Lead, Copper and Aluminium as Gamma Radiation Shielding Material through Experimental Measurements and Simulation Using MCNP Version 4c

2018 ◽  
Vol 9 (08) ◽  
pp. 20193-20206 ◽  
Author(s):  
Md. Akhlak Bin Aziz ◽  
Md. Faisal Rahman ◽  
Md. Mahidul Haque Prodhan
Keyword(s):  
Gamma Radiation ◽  
Sodium Iodide ◽  
Experimental Approach ◽  
Radiation Shielding ◽  
Test Material ◽  
Simulation Techniques ◽  
Radiation Sources ◽  
Simulation Monte Carlo ◽  
Shielding Material ◽  
Code Version

The paper compares  Lead, Copper and Aluminium as gamma radiation shielding material using both experimental and simulation techniques. Cs- 137 (662KeV), Na-22 (511KeV) and Na- 22(1274KeV) were used as gamma radiation sources and a sodium iodide (NaI) detector was used to detect the radiation. Variations were noted for detected gamma count rates by changing shielding material thickness. In the experimental approach, thickness was varied by placing sheets of a particular test material one by one. For simulation, Monte Carlo n- Particle (MCNP) code version 4c was used and the geometry of the whole experimental setup was plotted in it. The results were then compared for each test material and it was found that lead is the best shielding material for gamma radiation followed by copper and aluminium.

Advanced MCCI Modelling Based on Stringent Coupling of Thermal Hydraulics and Real Solution Thermochemistry in COSACO

2002 ◽  
Author(s):  
M. Nie ◽  
M. Fischer ◽  
G. Lohnert
Keyword(s):  
Phase Segregation ◽  
Real Solution ◽  
Volumetric Fraction ◽  
General Philosophy ◽  
Specific Sequence ◽  
Simultaneous Formation ◽  
Liquid Phases ◽  
Post Test ◽  
Reactor Materials ◽  
Code Version

The development of the MCCI code COSACO specifically addresses the ex-vessel MCCI phase of the core melt retention concept of the EPR. The general philosophy behind COSACO is a rigerous representation of thermochemical phenomena related to the MCCI. In particular, the code incorporates a real solution database to predict the simultaneous formation of solid and liquid phases as well as chemical reactions for a significant number melt constituents. This offers a great flexibility in terms of application to MCCIs involving reactor materials and to tests conducted with simulant melts. The approach to model heat transfer in oxidic melt pools is based on the phase segregation hypothesis. Besides a brief description of the principal models incorporated in COSACO, this paper highlights specific thermochemical effects that arose as part of post-test calculations of the tests MACE M3b and MACE M4 with this new code version. Particular attention is drawn to the effect of melt ejections on the pool temperature as well as to the evolution of solid volumetric fraction and of melt front progression during the MCCI. Finally, the application to a representative EPR specific sequence indicates that the principal objectives of the MCCI in the reactor pit can be safely fulfilled.

scholarly journals Gamma Shielding Experiment Simulation utilizing MCNPX Code

2021 ◽  
Vol 12 (2) ◽  
pp. 11-21
Author(s):  
Shafiqul Islam Faisal ◽  
Abi Muttaquin Bin Jalal Bayar
Keyword(s):  
Gamma Ray ◽  
Cost Effective ◽  
Radiation Shielding ◽  
Engineering Science ◽  
Gamma Source ◽  
Mcnpx Code ◽  
Radiation Sources ◽  
Absorbing Materials ◽  
Code Version

Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, radiation exposure involves people during the experiment. On the contrary, the simulation technique for examining radiation interactions is radio-logically safer, less timeconsuming, cost-effective, and applicable for all desired radiation sources. Through 48.86 mCi 662 keV Caesium-137 gamma-ray source; shielding experiment as well as simulation of it with MCNPX were performed for three shielding materials Lead, Copper, and Aluminum. These materials were placed in front of the gamma source and the emergent radiation was counted in a Geiger- Muller detector to understand the attenuation quality of these materials to each other. These courses of action were simulated utilizing the MCNPX code version 2.7.0 and the results likewise gave and looked at that of the experiment. There are huge similarities of shielding behavior between MCNPX simulation and experiments for the three absorbing materials. The modeled geometry of this MCNPX simulation could be used for future approaches of new designs and structures of radiation shielding, especially where no analogous experimental data exist Journal of Engineering Science 12(2), 2021, 11-21

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