Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7
Monte Carlo neutron transport codes are usually used to perform criticality calculations and to solve shielding problems due to their capability to model complex systems without major approximations. However, these codes demand high computational resources. The improvement in computer capabilities l...
Saved in:
Main Authors: | Diego Ferraro, Eduardo Villarino |
---|---|
Format: | Article |
Language: | English |
Published: |
Wiley
2011-01-01
|
Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2011/659406 |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Similar Items
-
Status of Serpent Monte Carlo code in 2024
by: Leppänen Jaakko, et al.
Published: (2025-01-01) -
Uncertainty Propagation Analysis for PWR Burnup Pin-Cell Benchmark by Monte Carlo Code McCARD
by: Ho Jin Park, et al.
Published: (2012-01-01) -
Review of JAEA’s Monte Carlo codes for nuclear reactor core analysis
by: Nagaya Yasunobu
Published: (2025-01-01) -
Status of GPU capabilities within the Shift Monte Carlo radiation transport code*
by: Biondo Elliott, et al.
Published: (2025-01-01) -
Monte Carlo Calculation of Fragment Distributions in Nuclear Reactions
by: A. Deppman, et al.
Published: (2012-01-01)