Serpent (software)
| Developer(s) | VTT |
|---|---|
| Stable release |
1.1.19
/ April 2, 2013 |
| Written in | C (programming language) |
| Operating system | Linux |
| Type | Computational physics |
| Website | http://montecarlo.vtt.fi/ |
Serpent is a continuous-energy Monte Carlo reactor physics code capable for highly detailed, three-dimensional burnup calculation. It is under current development at VTT Technical Research Centre of Finland since 2004 under the original name of "Probabilistic Scattering Game".[1] The code was originally developed with two-dimensional lattice physics calculations in mind; however, the code provides that the geometry can be generally expanded to three-dimensions.
The Serpent code makes use of an energy-grid restructuring of cross-sections and delta-ray tracking[2][3] for speed increases during the neutron transport simulation.
The Serpent code is often used for generating cross-sections for deterministic reactor physics codes.[4]
See also
- Nuclear reactor
- Nuclear engineering
- Neutron transport
- Nuclear reactor physics
- Monte Carlo N-Particle Transport Code
References
- ↑ Leppänen, Jaakko. "User Manual" (PDF). Retrieved 6 March 2013.
- ↑ Woodcock, E. R. (1965). "Techniques Used in the GEM Code for Monte Carlo Neutronics Calculations in Reactors and Other Systems of Complex Geometry.". Argonne National Laboratory (ANL-7050).
- ↑ Leppänen, J. (2010). "Performance of Woodcock Delta-Tracking in Lattice Physics Applications Using the Serpent Monte Carlo Reactor Physics Burnup Calculation Code.". Annals of Nuclear Energy. 37: 715–722.
- ↑ Fridman, E. (2011). "On the Use of the Serpent Monte Carlo Code for Few-group Cross Section Generation". Ann. Nucl. Energy (38).
External links
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