Serpent (software)
| Developer(s) | VTT Technical Research Centre of Finland |
|---|---|
| Stable release | 2.2.1
/ March 24, 2023 |
| Written in | C |
| Operating system | Linux |
| Platform | x86-64 |
| Type | Computational physics |
| Website | serpent |
Serpent is a continuous-energy multi-purpose three-dimensional Monte Carlo particle transport code. It is under development at VTT Technical Research Centre of Finland since 2004.[1] Serpent was originally known as Probabilistic Scattering Game (PSG) from 2004 to the first pre-release of Serpent 1 in October 2008.[2] The development of Serpent 2 was started in 2010.[3] The current stable version Serpent 2.2.0 was released in May 2022.[4]
Serpent was originally developed to be a simplified neutron transport code for reactor physics applications. Its main focus was on group constant generation with two-dimensional lattice calculations. Burnup calculation capability was included early on. Nowadays Serpent is used in a wide range of applications from the group constant generation[5] to coupled multi-physics applications, fusion neutronics and radiation shielding.[3] In addition to the original neutron transport capabilities, Serpent is able to perform photon transport.[3]
References[edit]
- ^ Leppänen, Jaakko; Pusa, Maria; Viitanen, Tuomas; Valtavirta, Ville; Kaltiaisenaho, Toni (2016). "The Serpent Monte Carlo code: Status, development and applications in 2013". Annals of Nuclear Energy. 82: 142–150. doi:10.1016/j.anucene.2014.08.024.
- ^ Leppänen, Jaakko. "Serpent – a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code User's Manual" (PDF). Retrieved 4 November 2018.
- ^ a b c Leppänen, Jaakko. "Greetings from the Serpent developer team & current status and future plans for Serpent 2" (PDF). Retrieved 4 November 2018.
- ^ "Serpent - A Monte Carlo Reactor Physics Burnup Calculation Code". Retrieved 3 June 2022.
- ^ Leppänen, Jaakko; Pusa, Maria; Fridman, Emil (2016). "Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code". Annals of Nuclear Energy. 96: 126–136. doi:10.1016/j.anucene.2016.06.007.