A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors

2022 ◽  
Vol 165 ◽  
pp. 108627
Author(s):  
Mona Ajami ◽  
Ali Kamkar ◽  
Mahdi Zangian ◽  
Abdolhamid Minuchehr ◽  
Ahmadreza Zolfaghari
2018 ◽  
Vol 3 (3) ◽  
pp. 473
Author(s):  
Bahdanovich R. B ◽  
Pázmán K. ◽  
Tikhomirov G. V.

Calculating the energy release in fuel elements is an important aspect of the modeling and design of nuclear reactors. Most of the energy is produced by fission, but a non-negligible percentage is coming from neutron capture reactions, such as (n, γ) or (n, α). We implement a previously developed method for the calculation of effective energy release using Serpent Monte Carlo code. We investigate the percentage of capture component in effective energy release for various models of VVER-1000 fuel: firstly, an equivalent cell, then fresh fuel assemblies of different compositions, differing in fuel enrichment and the presence of burnable absorbers. The results are compared to similar calculations previously done in MCNP 4 and MCU 5.


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 ◽  
...  

2016 ◽  
Vol 11 (1) ◽  
pp. 1600039 ◽  
Author(s):  
Dimitrios Meimaroglou ◽  
Prokopios Pladis ◽  
Costas Kiparissides

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