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|Program name||Package id||Status||Status date|
|SERPENT V2.2.0 -R-||NEA-1923/02||Tested||08-SEP-2022|
|Package ID||Orig. computer||Test computer|
Serpent is a three-dimensional continuous-energy Monte Carlo neutron and photon transport code, with built-in burnup calculation routine. The code is applicable to a wide range of reactor physics and radiation transport problems that can be divided into three categories:
Traditional reactor physics applications, including spatial homogenisation, criticality calculations, fuel cycle studies, research reactor modelling, validation of deterministic transport codes, etc.
Multi-physics simulations, i.e. coupled calculations with thermal hydraulics, CFD and fuel performance codes
Neutron and photon transport simulations for radiation dose rate calculations, shielding, fusion research and medical physics.
The code uses ACE format cross section libraries and other data derived from evaluated nuclear data files.
Serpent 2.2.X supersedes Serpent 1.1.X and Serpent 2.1.X.
Visit the Serpent website at http://montecarlo.vtt.fi
This version includes the addition of input and outputs generated using SERPENT v2 data. This differs from version /001 in that version /001 only contained inputs and outputs generated using only SERPENT v1 data.
RELATED EVALUATED NUCLEAR DATA FILES
Cross section and nuclear data libraries required for running SERPENT are freely available online at https://vtt.sharefile.eu/share/view/s21eeb4c656a54a75886952063591ff56/focf7068-d20d-4076-8044-1d0bf180b682
Cross section, decay and fission yield libraries based on the JEF-2.2, JEFF-3.1, JEFF-3.1.1, ENDF/B-VI.8 and ENDF/B-VII evaluated nuclear data files are also available through the NEA Data Bank, under the name “NEA-1854 ZZ SERPENT117-ACELIB” (https://www.oecd-nea.org/tools/abstract/detail/nea-1854/)
|Package ID||Status date||Status|
- J. Leppänen, et al. "The Serpent Monte Carlo code: Status, development and applications in 2013." Ann. Nucl. Energy, 82 (2015) 142-150.
More references at http://montecarlo.vtt.fi
Tested at the NEA Data Bank with:
MACHINE: CPS GitLab Cloud Service
OPERATING SYSTEM: Dockerized Ubuntu 20.04
COMPILER: gfortran v9 for the Ubuntu version tested
|Package ID||Computer language|
The software has been developed under Linux operating system using the C programming language. A C-compiler (gcc or similar) with standard system libraries is needed for building the source code. The GD open source graphics library is used for producing some graphical output. The source code can also be compiled without the GD functionality.
Keywords: Monte Carlo method, burnup calculation, continuous energy, criticality, fuel cycle analysis, fuel depletion, group constant generation, homogenisation, lattice physics, neutron transport.