Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC

2021 ◽  
Vol 151 ◽  
pp. 107946
Author(s):  
Farshid Reza ◽  
Md. Hossain Sahadath ◽  
Yasmin Akter
1986 ◽  
Vol 84 ◽  
Author(s):  
J-C. Dran ◽  
Y. Langevin ◽  
E. Doorhyee ◽  
J-C. Petit

AbstractA Monte-Carlo code has been developed to infer dissolution rates of silicate glasses from their chemical composition. The glasses are considered as solid solutions of oxides and silicates, being divided into elementary cells of network formers, in which network modifiers can be incorporated. The different types of cells are randomly distributed and a resistance capacity to dissolution is assigned to each cell. We have tested the case where each cell is removed in a constant time as soon as it is in contact with the solution and a second one where each cell is dissolved in a time depending on the number of already dissolved neighbor cells. The first hypothesis leads to a percolation threshold when the proportion of fast etching cells reaches 25 %. Above, the dissolution front progresses via contiguous channels of fast etching cells. In the second hypothesis the variations of the etch rate with the proportions of each component are much closer to a linear combination of individual etch rates. These predictions have been successfully compared to experimental data on different series of silicate glasses of increasing complexity. Such a treatment could be straightforwardly extended to nuclear glasses.


Author(s):  
Jan Prehradný ◽  
Martin Lovecký ◽  
Radek Škoda

Research of fuel depletion aims at development and introduction of advanced types of burnable absorbers (BA) in nuclear fuel. BAs compensate for the initial reactivity excess and consequently allow for lower power peaking factors and longer fuel cycles with higher fuel enrichments. The paper describes the comparison of selected BA elements (Gd, Eu, Er) for 3 different nuclear fuel types (VVER, PWR and SFR). The effect of harder VVER spectra and the effect of thermal vs fast neutron spectra is evaluated and commented. Uniformly distributed BAs in the fuel were assumed. Comparison calculations were performed with the newly developed UWB1 fast fuel depletion code and with the SERPENT Monte Carlo code. The comparison of UWB1 and SERPENT codes is included in the analysis. Next steps of improving the UWB1 code are suggested.


Kerntechnik ◽  
2015 ◽  
Vol 80 (4) ◽  
pp. 394-401 ◽  
Author(s):  
S. S. Aleshin ◽  
S. S. Gorodkov ◽  
A. I. Shcherenko

2020 ◽  
Vol 1548 ◽  
pp. 012020
Author(s):  
M De Simoni ◽  
M Fischetti ◽  
E Gioscio ◽  
M Marafini ◽  
R Mirabelli ◽  
...  

2021 ◽  
Vol 154 ◽  
pp. 108099
Author(s):  
Guanlin Shi ◽  
Yuchuan Guo ◽  
Conglong Jia ◽  
Zhiyuan Feng ◽  
Kan Wang ◽  
...  

2021 ◽  
Vol 196 ◽  
pp. 110566
Author(s):  
Jamila S. Alzahrani ◽  
Miysoon A. Alothman ◽  
Canel Eke ◽  
Hanan Al-Ghamdi ◽  
Dalal Abdulldh Aloraini ◽  
...  

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