Computer Programs
NEA-1923 SERPENT V2.2.0 -R-
last modified: 23-MAY-2022 | catalog | categories | new | search |

NEA-1923 SERPENT V2.2.0 -R-

SERPENT V2.2.0 -R-, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications

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1. NAME OR DESIGNATION OF PROGRAM

Serpent 2 Monte Carlo Code version 2.2.0.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name Package id Status Status date
SERPENT V2.2.0 -R- NEA-1923/01 Tested 23-MAY-2022

Machines used:

Package ID Orig. computer Test computer
NEA-1923/01 Linux-based PC Gitlab
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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:

  1. Traditional reactor physics applications, including spatial homogenisation, criticality calculations, fuel cycle studies, research reactor modelling, validation of deterministic transport codes, etc.

  2. Multi-physics simulations, i.e. coupled calculations with thermal hydraulics, CFD and fuel performance codes

  3. 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

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4. METHODS

The transport simulation is based on the continuous-energy Monte Carlo method. Other methodologies include a built-in depletion solver based on the Chebyshev Rational Approximation Method (CRAM) and a response matrix method-based importance solver for variance reduction purposes.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Running Monte Carlo simulations for complex systems may require considerable computer capacity. Large-scale problems may be subject to limitations with computer memory.

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6. TYPICAL RUNNING TIME

Case-dependent.

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7. UNUSUAL FEATURES OF THE PROGRAM

Serpent has been specifically designed for reactor physics applications, but the applicability is not limited to fission reactor modelling.

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8. RELATED OR AUXILIARY PROGRAMS

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/)

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9. STATUS
Package ID Status date Status
NEA-1923/01 23-MAY-2022 Tested restricted
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10. REFERENCES

- 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

NEA-1923/01, included references:
- All SERPENT documentation is available on-line in the Serpent wiki
https://serpent.vtt.fi/mediawiki/index.php/Main_Page
- Jaakko Leppanen:
Serpent - a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation
Code, User's Manual (June 18, 2015)
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11. HARDWARE REQUIREMENTS

Tested at the NEA Data Bank with:

 

LINUX:

    • MACHINE: CPS GitLab Cloud Service

    • OPERATING SYSTEM: Dockerized Ubuntu 20.04

    • COMPILER: gfortran v9 for the Ubuntu version tested

 

OTHER: - GitLab source repository located at http://git.oecd-nea.org/databank/cps/serpent/serpent-2.2.0 (with restricted access)

         Testing pipeline located at http://git.oecd-nea.org/databank/cps/serpent/testing-pipeline (with restricted access)

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1923/01 C-LANGUAGE
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13. SOFTWARE REQUIREMENTS

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.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Serpent has been succesfully run in Cygwin, but this option is not supported by the developers.

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15. NAME AND ESTABLISHMENT OF AUTHORS

VTT Technical Research Centre of Finland, Ltd

Kivimiehentie 3, Espoo, FI-02044 VTT, Finland

Contact for commercial use: IP.agreements (at) vtt.fi

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16. MATERIAL AVAILABLE
NEA-1923/01
SERPENT V2.2.0-info-file.txt --- This information file
Serpent_2.2.X_README.pdf --- Readme file
Serpent_manual.pdf ----- Serpent 1 User's Manual
\src ------------------- Source files, Makefile and Version history text file
\util\xsdirconvert.pl -- Script to convert xsdir (ACE) file to Serpent format
\NEA_examples-2.2.0 ---- NEA Tests
   \BWR             BWR lattice calculation
   \CANDU           CANDU lattice calculation
   \EBR_II          2D Simplified 4-HEX super-cell model-like EBR-II
   \GODIVA          Godiva sphere
   \HTGR_BURNUP     HTGR burnup calculation
   \PC_BURNUP       Pin-cell burnup calculation
   \PU_FLATTOP      Critical Pu-Flattop experiment
                    (PU-MET-FAST-006 from the NEA ICSBEP Handbook)
   \PWR_BURNUP      PWR assembly burnup calculation
   \PWR_MOX         Mixed UOX/MOX PWR lattice calculation
   \STACY           STACY critical experiment
                    (LEU-SOL-THERM-007 from the NEA ICSBEP Handbook)
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: Monte Carlo method, burnup calculation, continuous energy, criticality, fuel cycle analysis, fuel depletion, group constant generation, homogenisation, lattice physics, neutron transport.